[Federal Register Volume 81, Number 21 (Tuesday, February 2, 2016)]
[Notices]
[Pages 5495-5505]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-01771]
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NUCLEAR REGULATORY COMMISSION
[NRC-2016-0019]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice.
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SUMMARY: Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954,
as amended (the Act), the U.S. Nuclear Regulatory Commission (NRC) is
publishing this regular biweekly notice. The Act requires the
Commission to publish notice of any amendments issued, or proposed to
be issued, and grants the Commission the authority to issue and make
immediately effective any amendment to an operating license or combined
license, as applicable, upon a determination by the Commission that
such amendment involves no significant hazards consideration,
notwithstanding the pendency before the Commission of a request for a
hearing from any person.
This biweekly notice includes all notices of amendments issued, or
proposed to be issued from January 5, 2016, to January 15, 2016. The
last biweekly notice was published on January 19, 2016.
DATES: Comments must be filed by March 3, 2016. A request for a hearing
must be filed by April 4, 2016.
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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2016-0019. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected].
Mail comments to: Cindy Bladey, Office of Administration,
Mail Stop: OWFN-12-H08, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
For additional direction on obtaining information and submitting
comments, see ``Obtaining Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
FOR FURTHER INFORMATION CONTACT: Janet Burkhardt, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001; telephone: 301-415-1384, email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Obtaining Information and Submitting Comments
A. Obtaining Information
Please refer to Docket ID NRC-2016-0019 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 Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2016-0019.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may obtain publicly-available documents online in the
ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS,
please contact the NRC's Public Document Room (PDR) reference staff at
1-800-397-4209, 301-415-4737, or by email to [email protected]. The
ADAMS accession number for each document referenced (if it is available
in ADAMS) is provided the first time that it is mentioned in the
SUPPLEMENTARY INFORMATION section of 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-2016-0019, facility name, unit
number(s), 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 posts all comment submissions at http://www.regulations.gov, as well as entering the comment submissions into
ADAMS. The NRC does not routinely edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information that they do not want to be
publicly disclosed in their comment submission. Your request should
state that the NRC does not routinely edit comment submissions to
remove such information before making the comment submissions available
to the public or entering the comment submissions into ADAMS.
II. 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, (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 should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
[[Page 5496]]
A. Opportunity To Request a Hearing and Petition for Leave To Intervene
Within 60 days after the date of publication of this notice, any
person(s) whose interest may be affected by this action may file a
request for a hearing and a petition to intervene with respect to
issuance of the amendment to the subject facility operating license or
combined license. Requests for a hearing and a petition for leave to
intervene shall be filed in accordance with the Commission's ``Agency
Rules of Practice and Procedure'' in 10 CFR part 2. Interested
person(s) should consult a current copy of 10 CFR 2.309, which is
available at the NRC's PDR, located at One White Flint North, Room O1-
F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The
NRC's regulations are accessible electronically from the NRC Library on
the NRC's Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is
filed within 60 days, the Commission or a presiding officer designated
by the Commission or by the Chief Administrative Judge of the Atomic
Safety and Licensing Board Panel, will rule on the request and/or
petition; and the Secretary or the Chief Administrative Judge of the
Atomic Safety and Licensing Board will issue a notice of a hearing or
an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/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 requestor's/petitioner's interest. The petition must
also set forth the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include sufficient information to show that
a genuine dispute exists with the applicant on a material issue of law
or fact. Contentions shall be limited to matters within the scope of
the amendment under consideration. The contention must be one which, if
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing with respect to resolution of that person's admitted
contentions, including the opportunity to present evidence and to
submit a cross-examination plan for cross-examination of witnesses,
consistent with NRC regulations, policies and procedures.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Requests for hearing,
petitions for leave to intervene, and motions for leave to file new or
amended contentions that are filed after the 60-day deadline will not
be entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the three factors in 10
CFR 2.309(c)(1)(i)-(iii).
If a hearing is requested, and the Commission has not made a final
determination on the issue of no significant hazards consideration, the
Commission will make a final determination on the issue of no
significant hazards consideration. The final determination will serve
to decide when the hearing is held. If the final determination is that
the amendment request involves no significant hazards consideration,
the Commission may issue the amendment and make it immediately
effective, notwithstanding the request for a hearing. Any hearing held
would take place after issuance of the amendment. If the final
determination is that the amendment request involves a significant
hazards consideration, then any hearing held would take place before
the issuance of any amendment unless the Commission finds an imminent
danger to the health or safety of the public, in which case it will
issue an appropriate order or rule under 10 CFR part 2.
A State, local governmental body, Federally-recognized Indian
Tribe, or agency thereof, may submit a petition to the Commission to
participate as a party under 10 CFR 2.309(h)(1). The petition should
state the nature and extent of the petitioner's interest in the
proceeding. The petition should be submitted to the Commission by April
4, 2016. 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 for leave
to intervene set forth in this section, except that under Sec.
2.309(h)(2) a State, local governmental body, or Federally-recognized
Indian Tribe, or agency thereof does not need to address the standing
requirements in 10 CFR 2.309(d) if the facility is located within its
boundaries. A State, local governmental body, Federally-recognized
Indian Tribe, or agency thereof may also have the opportunity to
participate under 10 CFR 2.315(c).
If a hearing is granted, any person who does not wish, or is not
qualified, to become a party to the proceeding may, in the discretion
of the presiding officer, be permitted to make a limited appearance
pursuant to the provisions of 10 CFR 2.315(a). A person making a
limited appearance may make an oral or written statement of position on
the issues, but may not otherwise participate in the proceeding. A
limited appearance may be made at any session of the hearing or at any
prehearing conference, subject to the limits and conditions as may be
imposed by the presiding officer. Persons desiring to make a limited
appearance are requested to inform the Secretary of the Commission by
April 4, 2016.
B. Electronic Submissions (E-Filing)
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC's E-Filing rule (72 FR 49139;
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the internet, or in some
cases to mail copies on electronic storage media. Participants may not
[[Page 5497]]
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
To comply with the procedural requirements of E-Filing, at least 10
days prior to the filing deadline, the participant should contact the
Office of the Secretary by email at [email protected], or by
telephone at 301-415-1677, to request (1) a digital identification (ID)
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (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 Web site at http://www.nrc.gov/site-help/e-submittals/getting-started.html. System requirements for accessing
the E-Submittal server are detailed in the NRC's ``Guidance for
Electronic Submission,'' which is available on the agency's public Web
site at http://www.nrc.gov/site-help/e-submittals.html. Participants
may attempt to use other software not listed on the Web site, but
should note that the NRC's E-Filing system does not support unlisted
software, and the NRC Meta System Help Desk will not be able to offer
assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC's
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with NRC guidance
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's Office of the General Counsel and any
others who have advised the Office of the Secretary that they wish to
participate in the proceeding, so that the filer need not serve the
documents on those participants separately. Therefore, applicants and
other participants (or their counsel or representative) must apply for
and receive a digital ID certificate before a hearing request/petition
to intervene is filed so that they can obtain access to the document
via the E-Filing system.
A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System
Help Desk through the ``Contact Us'' link located on the NRC's public
Web site 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 Meta System Help Desk is available between 8 a.m. and 8 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
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, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland
20852, Attention: Rulemaking and Adjudications Staff. Participants
filing a document in this manner are responsible for serving the
document on all other participants. Filing is considered complete by
first-class mail as of the time of deposit in the mail, or by courier,
express mail, or expedited delivery service upon depositing the
document with the provider of the service. A presiding officer, having
granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in the
NRC's electronic hearing docket which is available to the public at
http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social security numbers,
home addresses, or home phone numbers in their filings, unless an NRC
regulation or other law requires submission of such information.
However, in some instances, a request to intervene will require
including information on local residence in order to demonstrate a
proximity assertion of interest in the proceeding. With respect to
copyrighted works, except for limited excerpts that serve the purpose
of the adjudicatory filings and would constitute a Fair Use
application, participants are requested not to include copyrighted
materials in their submission.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Requests for hearing,
petitions for leave to intervene, and motions for leave to file new or
amended contentions that are filed after the 60-day deadline will not
be entertained absent a determination by the presiding officer that the
filing demonstrates good cause by satisfying the three factors in 10
CFR 2.309(c)(1)(i)-(iii).
For further details with respect to these license amendment
applications, see the application for amendment which is available for
public inspection in ADAMS and at the NRC's PDR. For additional
direction on accessing information related to this document, see the
``Obtaining Information and Submitting Comments'' section of this
document.
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: November 19, 2015. A publicly available
version is in ADAMS under Accession No. ML15324A309.
Description of amendment request: The proposed amendments would
revise LSCS Technical Specifications
[[Page 5498]]
(TS) Section 2.1.1, ``Reactor Core SLs,'' to reflect a lower reactor
steam dome pressure stated for Reactor Core Safety Limits (SLs) 2.1.1.1
and 2.1.1.2. Specifically, the proposed amendment will reduce the
reactor steam dome pressure in TS SLs 2.1.1.1 and 2.1.1.2 from 785 psig
[pound per square inch gage] to 685 psig. This change to TS Section
2.1.1 was identified as a result of General Electric Part 21 report
SC05-03, ``Potential to Exceed Low Pressure Technical Specification
Safety Limit.'' This change is valid for the NRC-approved pressure
range pertinent to the critical power correlations applied to the fuel
types in use at LSCS.
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 to the reactor steam dome pressure in the
LSCS Reactor Core Safety Limits TS 2.1.1.1 and 2.1.1.2 does not
alter the use of the analytical methods used to determine the safety
limits that have been previously reviewed and approved by the NRC.
The proposed change is in accordance with an NRC approved critical
power correlation methodology, and as such, maintains required
safety margins. The proposed change does not adversely affect
accident initiators or precursors, nor does it alter the design
assumptions, conditions, or configuration of the facility or the
manner in which the plant is operated and maintained.
The proposed change does not alter or prevent the ability of
structures, systems, and components (SSCs) from performing their
intended function to mitigate the consequences of an initiating
event within the assumed acceptance limits. The proposed change does
not require any physical change to any plant SSCs nor does it
require any change in systems or plant operations. The proposed
change is consistent with the safety analysis assumptions and
resultant consequences.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed reduction in the reactor dome pressure safety limit
from 785 psig to 685 psig is a change based upon previously approved
documents and does not involve changes to the plant hardware or its
operating characteristics. As a result, no new failure modes are
being introduced.
There are no hardware changes nor are there any changes in the
method by which any plant systems perform a safety function. No new
accident scenarios, failure mechanisms, or limiting single failures
are introduced as a result of the proposed change.
The proposed change does not introduce any new accident
precursors, nor does it involve any physical plant alterations or
changes in the methods governing normal plant operation. Also, the
change does not impose any new or different requirements or
eliminate any existing requirements. The change does not alter
assumptions made in the safety analysis.
Therefore, the proposed change does not create the possibility
of a new or different kind of accident from any previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The margin of safety is established through the design of the
plant structures, systems, and components, and through the
parameters for safe operation and setpoints for the actuation of
equipment relied upon to respond to transients and design basis
accidents.
Evaluation of the 10 CFR part 21 condition by General Electric
determined that since the Minimum Critical Power Ratio improves
during the PRFO [Pressure Regulator Failure Maximum Demand (Open)]
transient, there is no decrease in the safety margin and therefore
there is not a threat to fuel cladding integrity.
The proposed change in reactor dome pressure supports the
current safety margin, which protects the fuel cladding integrity
during a depressurization transient, but does not change the
requirements governing operation or availability of safety equipment
assumed to operate to preserve the margin of safety. The change does
not alter the behavior of plant equipment, which remains unchanged.
The proposed change to Reactor Core Safety Limits 2.1.1.1 and
2.1.1.2 is consistent with and within the capabilities of the
applicable NRC approved critical power correlation for the fuel
designs in use at LSCS, Units 1 and 2. No setpoints at which
protective actions are initiated are altered by the proposed change.
The proposed change does not alter the manner in which the
safety limits are determined. This change is consistent with plant
design and does not change the TS operability requirements; thus,
previously evaluated accidents are not affected by this proposed
change.
Therefore, the proposed changes do not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
requested amendments involve no significant hazards consideration.
Attorney for licensee: Bradley J. Fewell, Associate General
Counsel, Exelon Nuclear, 4300 Winfield Road, Warrenville, IL 60555.
NRC Acting Branch Chief: Justin C. Poole.
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
277 and 50-278, Peach Bottom Atomic Power Station, Units 2 and 3, York
and Lancaster Counties, Pennsylvania
Date of amendment request: December 3, 2015. A publicly-available
version is in ADAMS under Accession No. ML15337A413.
Description of amendment request: The amendments would revise the
technical specification (TS) surveillance requirements (SRs) associated
with the emergency diesel generator (EDG) fuel oil transfer system.
Specifically, the amendments would allow for the crediting of manual
actions, in lieu of automatic actions, without having to declare the
EDGs inoperable.
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 will revise SR 3.8.1.6 by adding a note to
allow for procedurally controlled simple manual actions associated
with the fuel oil transfer system without having to declare the EDG
inoperable [under] administrative control. The fuel oil transfer
system is required to support continuous operation of standby power
sources. The surveillance provides assurance that the fuel oil
transfer system is OPERABLE. The fuel oil transfer system is not an
initiator of any event previously evaluated. Therefore, the
probability of any accident previously evaluated is not increased.
In the event of an accident, if simple manual actions were
necessary to restore the automatic feature of the EDG day tank fill,
analysis shows that significant margin exists to ensure that EDG
operability would not be adversely affected. Although the proposed
change to allow simple manual actions could introduce additional
potential malfunctions, such that human error could result in the
potential to improperly realign the fuel oil transfer system during
a DBA [design-basis accident], the improper realignment would be
detected when the transfer of fuel oil from the storage tank to the
day tank did not occur as expected and the error would be corrected
prior to having a significant impact.
The proposed change does not involve any physical changes to the
structures, systems, or components (SSCs) in the plant. Further the
proposed change does not alter or prevent the ability of SSCs from
performing their intended function to mitigate the consequences of
an event.
[[Page 5499]]
The proposed change is consistent with NRC regulatory
requirements regarding the content of plant TS as identified in 10
CFR 50.36. Additionally, the proposed change is consistent with
NUREG-1433, ``Standard Technical Specifications General Electric
BWR/4 Plants,'' in that the word `automatically' is bracketed (i.e.,
optional or as required by plant design).
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed change does not alter the physical design, safety
limits, or safety analysis assumptions associated with the operation
of the plant. Accordingly, the change does not introduce any new
accident initiators, nor does it reduce or adversely affect the
capabilities of any plant structure, system, or component to perform
their safety function. Consequently, there are no new initiators
that could result in a new or different kind of 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?
Response: No.
The proposed change conforms to NRC regulatory guidance
regarding the content of plant Technical Specifications. The
proposed change does not alter the physical design, safety limits,
or safety analysis assumptions associated with the operation of the
plant. The proposed change has no adverse impact on current Safety
Limits, Limiting Safety System Settings, Limiting Control Settings,
Limiting Conditions for Operation, Surveillance Requirements, Design
Features, or Administrative Controls.
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: Tamra Domeyer, Associate General Counsel,
Exelon Generation Company, LLC, 4300 Winfield Rd., Warrenville, IL
60555.
NRC Branch Chief: Douglas A. Broaddus.
South Carolina Electric and Gas Company, Docket Nos. 52-027 and 52-028,
Virgil C. Summer Nuclear Station (VCSNS), Units 2 and 3, Fairfield
County, South Carolina
Date of amendment request: December 17, 2015, and supplemented by
letter dated January 11, 2016. Publicly-available versions are in ADAMS
under Accession Nos. ML15351A452 and ML16011A500, respectively.
Description of amendment request: The proposed changes, if
approved, would amend Combined License Nos. NPF-93 and NPR-94 for
VCSNS, Units 2 and 3, respectively. The requested amendment proposes to
change the design of the auxiliary building Wall 11 and other changes
to the licensing basis for the use of Category II structures, such as
Wall 11.2 in the turbine building. The changes in the proposed
amendment are located primarily in the VCSNS Updated Final Safety
Analysis Report (UFSAR) Tier 2* and Tier 2 information, and also
require conforming changes to a license condition.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed changes do not adversely affect the operation of
any systems or equipment inside or outside the auxiliary building
that could initiate or mitigate abnormal events, e.g., accidents,
anticipated operational occurrences, earthquakes, floods, tornado
missiles, and turbine missiles, or their safety or design analyses,
evaluated in the UFSAR. The changes do not adversely affect any
design function of the auxiliary building or the systems and
equipment contained therein. The ability of the affected auxiliary
building [main steam isolation valve] MSIV compartments to withstand
the pressurization effects from the design basis pipe rupture is not
adversely affected by the removal of the Wall 11 upper vent
openings, because vents at these locations are not credited in the
subcompartment pressurization analysis. MSIV compartment
temperatures following the limiting one square foot pipe rupture
with the vent openings removed remain acceptably within the envelope
for environmental qualification of equipment in the compartments.
The credit of seismic Category II Wall 11.2 as a [high energy line
break] HELB barrier and the seismic Category II turbine building
first bay and associated missile barriers to protect Wall 11
openings from tornado missiles continues to provide adequate
protection of structures, systems, and components (SSCs) required to
safely shut down the plant, as these structures are designed to the
same requirements as seismic Category I structures, and with the
additional HELB loadings assumed, remain well within the applicable
acceptance criteria.
Therefore, the proposed activity does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create the possibility of a new
or different kind of accident from any accident previously
evaluated?
Response: No.
The proposed changes do not change the design function of the
auxiliary building or of any of the systems or equipment in the
auxiliary building or elsewhere within the Nuclear Island structure.
These proposed changes do not introduce any new equipment or
components that would result in a new failure mode, malfunction or
sequence of events that could affect safety-related or nonsafety-
related equipment. This activity will not allow for a new fission
product release path, result in a new fission product barrier
failure mode, or create a new sequence of events that would result
in significant fuel cladding failures.
Therefore, this activity does not create the possibility of a
new or different kind of accident from any previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The margin of safety for the design of the auxiliary building is
maintained through continued use of the current codes and standards
as stated in the UFSAR and adherence to the assumptions used in the
analyses of this structure and the events associated with this
structure. The auxiliary building will continue to maintain a
seismic Category I rating which preserves the current structural
safety margins. The 3-hour fire rating requirements for the impacted
auxiliary building walls are maintained. The Wall 11 upper vents are
not credited in the subcompartment pressurization analysis and the
remaining vents and pressure relief devices provide sufficient
venting to maintain the MSIV compartment pressures below the design
limit and design basis. The credit of turbine building Wall 11.2 as
a HELB barrier provides protection of Wall 11 from selected dynamic
effects, which in turn provides that essential SSCs remain protected
from the effects of postulated HELB events. The credit of the
seismic Category II turbine building first bay and associated
missile barriers to provide protection of Wall 11 openings from
tornado missiles provides sufficient protection for the essential
SSCs located in the auxiliary building in the vicinity of Wall 11
from the effects of external missiles. Thus the requested changes
will not adversely affect any safety-related equipment, design code,
function, design analysis, safety analysis input or result, or
design/safety margin. No safety analysis or design basis acceptance
limit/criterion is challenged or exceeded by the requested change,
thus, no margin of safety is reduced.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
[[Page 5500]]
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Ms. Kathryn M. Sutton, Morgan, Lewis &
Bockius LLC, 1111 Pennsylvania Avenue NW., Washington, DC 20004-2514.
NRC Acting Branch Chief: John McKirgan.
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 16, 2015. A publicly-available
version is in ADAMS under Accession No. ML15320A464.
Description of amendment request: The requested amendment proposes
to depart from Tier 2* information in the Updated Final Safety Analysis
Report related to the construction methods used for the composite
floors and roof of the auxiliary building.
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 design functions of the nuclear island structures are to
provide support, protection, and separation for the seismic Category
I mechanical and electrical equipment located in the nuclear island.
The nuclear island structures are structurally designed to meet
seismic Category I requirements as defined in Regulatory Guide 1.29.
The use of [American Concrete Institute (ACI)] 349 and [American
Institute of Steel Construction (AISC)] N690 provides criteria for
the design, qualification, fabrication, and inspection of composite
steel beam floors and roof in the auxiliary building. These
structures continue to meet the applicable portions of ACI 349 and
AISC N690. The proposed change does not have an adverse impact on
the response of the nuclear island structures to safe shutdown
earthquake ground motions or loads due to anticipated transients or
postulated accident conditions. The change does not impact the
support, design, or operation of mechanical and fluid systems. There
is no change to plant systems or the response of systems to
postulated accident conditions. There is no change to the predicted
radioactive releases due to normal operation or postulated accident
conditions. The plant response to previously evaluated accidents or
external events is not adversely affected, nor does the change
described create any new accident precursors.
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 change revises the description of the construction
of composite steel beam floors and roof in the auxiliary building.
The proposed change does not change the design function, support,
design, or operation of mechanical and fluid systems. The proposed
change does not result in a new failure mechanism for the pertinent
structures or new accident precursors. As a result, the design
function of the structures is not adversely affected by the proposed
change.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any accident
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
The proposed change is consistent with ACI 349 and AISC N690.
The design and construction of the auxiliary building floors and
roof remain in conformance with the requirements in ACI 349 and AISC
N690.
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 Acting Branch Chief: John McKirgan.
Susquehanna Nuclear, LLC, Docket Nos. 50-387 and 50-388, Susquehanna
Steam Electric Station, Units 1 and 2 (SSES), Luzerne County,
Pennsylvania
Date of amendment request: March 19, 2015, as supplemented by
letters dated October 15, 2015, October 16, 2015, and January 8, 2016.
Publicly-available versions are in ADAMS under Package Accession Nos.
ML15091A657, ML15296A048, and ML15296A057, and Accession No.
ML16011A103, respectively.
Description of amendment request: The NRC staff previously made a
proposed determination that the amendment request dated March 19, 2015,
involved no significant hazards consideration (80 FR 38762; July 7,
2015). Subsequently, the supplemental letter dated October 15, 2015,
provided additional information that expanded the scope of the
application as originally noticed. Accordingly, this notice supersedes
the previous notice in its entirety. The amendments would revise the
Emergency Plan for SSES to adopt the Nuclear Energy Institute's (NEI's)
revised emergency action level (EAL) scheme described in NEI 99-01,
Revision 6, ``Development of Emergency Action Levels for Non-Passive
Reactors'' (ADAMS Accession No. ML12326A805), which was endorsed by the
NRC as documented in NRC letter dated March 28, 2013 (ADAMS Accession
No. ML12346A463). Supplemental changes in these amendments were
discussed in a September 23, 2015, public meeting held with Susquehanna
Nuclear, LLC. The public meeting summary was issued October 9, 2015,
and is available in ADAMS under Accession No. ML15278A492. The
additional information, and the changes discussed at the public
meeting, are included in the two Susquehanna Nuclear, LLC letters dated
October 15, 2015, and October 16, 2015. The revised Emergency Plan
includes the appropriate plant-specific changes as a result of an
emergency operating procedure upgrade project and corrective action in
response to an NRC Emergency Preparedness White Finding, documented in
NRC Inspection Report No. 05000387/2015504 and 05000388/2015504, dated
June 22, 2015 (ADAMS Accession Nos. ML15173A297 and ML15181A332).
On June 1, 2015, the NRC staff issued an amendment changing the
name on the SSES license from PPL Susquehanna, LLC to Susquehanna
Nuclear, LLC. This amendment was issued subsequent to an order issued
on April 10, 2015, to SSES, approving an indirect license transfer.
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, along with NRC edits in square
brackets:
1. Does the proposed change involve a significant increase in
the probability or consequences of any accident previously
evaluated?
Response: No.
The proposed changes to the EAL scheme to adopt the NRC-endorsed
guidance in NEI 99-01, Revision 6, ``Development of Emergency Action
Levels for Non-Passive Reactors,'' [and the additional plant-
specific Emergency Plan changes] do not reduce the capability to
meet the emergency planning requirements established in 10 CFR 50.47
and 10 CFR 50, Appendix E. The proposed changes do not reduce the
functionality, performance, or capability of the ERO [Emergency
Response Organization] to
[[Page 5501]]
respond in mitigating the consequences of any design basis accident.
The probability of a reactor accident requiring implementation
of Emergency Plan EALs has no relevance in determining whether the
proposed changes to the EALs reduce the effectiveness of the
Emergency Plan. As discussed in Section I.D, ``Planning Basis,'' of
NUREG-0654, Revision 1, ``Criteria for Preparation and Evaluation of
Radiological Emergency Response Plans and Preparedness in Support of
Nuclear Power Plants'';
. . . The overall objective of emergency response plans is to
provide dose savings (and in some cases immediate life saving) for a
spectrum of accidents that could produce offsite doses in excess of
Protective Action Guides (PAGs). No single specific accident
sequence should be isolated as the one for which to plan because
each accident could have different consequences, both in nature and
degree. Further, the range of possible selection for a planning
basis is very large, starting with a zero point of requiring no
planning at all because significant offsite radiological accident
consequences are unlikely to occur, to planning for the worst
possible accident, regardless of its extremely low likelihood. . . .
Therefore, risk insights are not considered for any specific
accident initiation or progression in evaluating the proposed
changes.
The proposed changes do not involve any physical changes to
plant equipment or systems, nor do they alter the assumptions of any
accident analyses. The proposed changes do not adversely affect
accident initiators or precursors nor do they alter the design
assumptions, conditions, and configuration or the manner in which
the plants are operated and maintained. The proposed changes do not
adversely affect the ability of Structures, Systems, or Components
(SSCs) to perform their intended safety functions in mitigating the
consequences of an initiating event within the assumed acceptance
limits.
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed changes to the EAL scheme to adopt the NRC-endorsed
guidance in NEI 99-01, Revision 6, [and the additional plant-
specific Emergency Plan changes] do not involve any physical changes
to plant systems or equipment. The proposed changes do not involve
the addition of any new plant equipment. The proposed changes will
not alter the design configuration, or method of operation of plant
equipment beyond its normal functional capabilities. All ERO
functions will continue to be performed as required. The proposed
changes do not create any new credible failure mechanisms,
malfunctions, or accident initiators.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from those that have been
previously evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
The proposed changes to the EAL scheme to adopt the NRC-endorsed
guidance in NEI 99-01, Revision 6, [and the additional plant-
specific Emergency Plan changes] do not alter or exceed a design
basis or safety limit. There is no change being made to safety
analysis assumptions, safety limit, or limiting safety system
settings that would adversely affect plant safety as a result of the
proposed changes. There are no changes to setpoints or environmental
conditions of any SSC or the manner in which any SSC is operated.
Margins of safety are unaffected by the proposed changes to adopt
the NEI 99-01, Revision 6 EAL scheme guidance. The applicable
requirements of 10 CFR 50.47 and 10 CFR 50, Appendix E will continue
to be met.
Therefore, the proposed changes do not involve any 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: Damon D. Obie, Associate General Counsel,
Talen Energy Supply, LLC, 835 Hamilton St., Suite 150, Allentown, PA
18101.
NRC Branch Chief: Douglas A. Broaddus.
Tennessee Valley Authority, Docket No. 50-391, Watts Bar Nuclear Plant
(WBN), Unit 2, Rhea County, Tennessee
Date of amendment request: December 15, 2015. A publicly-available
version is in ADAMS under Accession No. ML15350A250.
Brief description of amendment request: The amendment would revise
the technical specification (TS) surveillance requirements (SRs) for
the WBN, Unit 2, ice condenser lower inlet doors.
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 consequence of an accident previously evaluated?
Response: No.
The ice condenser is a passive heat removal plant feature. The
proposed amendment to the TS 3.6.12 does not change the design,
physical features or the function of the ice condenser or the ice
condenser doors. The ice condenser is not an accident initiator,
thus the proposed amendment does not increase the probability of an
accident previously evaluated.
The ice condenser is credited in mitigating the consequences of
postulated Design Basis Accidents (DBAs) and remains capable of
performing its design basis functions. The proposed amendment to the
SRs during the first cycle of WBN Unit 2 operation does not change
the ice condenser configuration or how it behaves in the event of a
DBA. Thus it is concluded that a significant increase in the
consequences of an accident previously evaluated will not occur as a
result of the proposed amendment.
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 amendment does not create the possibility of a new
or different kind of accident from any accident previously
evaluated. The proposed amendment does not introduce any new modes
of plant operation, change the design function of the ice condenser
or any other Structure System or Component (SSC), or change the mode
of operation of the ice condenser or any other SSC. There are no new
equipment failure modes or malfunctions created as the ice condenser
and ice condenser lower inlet doors continue to operate in the same
manner assumed in the accident analysis. The ice condenser is a
passive post-accident heat removal feature that is not an accident
initiator.
Therefore, the proposed amendment does not create the
possibility of a new or different kind of accident from any
previously evaluated.
3. Does the proposed amendment involve a significant reduction
in a margin of safety?
Response: No.
Ice condensers have been in-service at nine nuclear units in the
United States for many years. Operating experience has shown that an
18-month surveillance frequency for evaluating operability is
appropriate for the lower inlet doors. The proposed amendment to
perform a revised schedule of lower inlet door surveillances in the
first cycle before transitioning to the standard 18-month
surveillance frequency does not result in a significant reduction in
the margin of safety.
Therefore, since there is no adverse impact of this amendment on
the WBN Unit 2 safety analysis, there is no significant reduction in
the margin of safety of the plant.
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: Scott A. Vance, Associate General Counsel,
Nuclear, Tennessee Valley Authority, 400 West Summit Hill Drive, WT 6A-
K, Knoxville, TN 37902.
NRC Branch Chief: Benjamin G. Beasley.
[[Page 5502]]
III. Notice of Issuance of Amendments to Facility Operating Licenses
and Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR Chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, proposed no
significant hazards consideration determination, and opportunity for a
hearing in connection with these actions, was published in the Federal
Register as indicated.
Unless otherwise indicated, the Commission has determined that
these amendments satisfy the criteria for categorical exclusion in
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b),
no environmental impact statement or environmental assessment need be
prepared for these amendments. If the Commission has prepared an
environmental assessment under the special circumstances provision in
10 CFR 51.22(b) and has made a determination based on that assessment,
it is so indicated.
For further details with respect to the action see (1) the
applications for amendment, (2) the amendment, and (3) the Commission's
related letter, Safety Evaluation and/or Environmental Assessment as
indicated. All of these items can be accessed as described in the
``Obtaining Information and Submitting Comments'' section of this
document.
Duke Energy Progress, Inc., Docket Nos. 50-325 and 50-324, Brunswick
Steam Electric Plant, Units 1 and 2, Brunswick County, North Carolina
Date of amendment request: January 30, 2015, as supplemented by
letter dated November 23, 2015.
Brief description of amendments: The amendments authorized the
upgrade of the emergency action level scheme for each unit based on the
Nuclear Energy Institute (NEI) document NEI 99-01, Revision 6,
``Development of Emergency Action Levels for Non-Passive Reactors,''
dated November 2012. NEI 99-01, Revision 6, was endorsed by the NRC by
letter dated March 28, 2013.
Date of issuance: January 8, 2016.
Effective date: As of the date of issuance and shall be implemented
within 180 days of issuance.
Amendment Nos.: 268 (Unit 1) and 296 (Unit 2). A publicly-available
version is in ADAMS under Accession No. ML15344A153; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Renewed Facility Operating License Nos. DPR-71 and DPR-62:
Amendments revised the Renewed Facility Operating Licenses.
Date of initial notice in Federal Register: April 28, 2015 (80 FR
23602). The supplemental letter dated November 23, 2015, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 8, 2016.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket Nos. 50-003, 50-247, and 50-
286, Indian Point Nuclear Generating Station (IP), Unit Nos. 1, 2, and
3, and Docket No. 72-51 for IP Independent Spent Fuel Storage
Installation (ISFSI), Westchester County, New York
Date of application for amendments: August 20, 2013, as
supplemented by letters dated November 21, 2013, and May 13 and July
24, 2014.
Brief description of amendments: The amendments modified the
licenses to reflect a grant of Section 161A of the Atomic Energy Act,
to authorize the licensee the authority to possess and use certain
firearms, ammunition, and other devices such as large-capacity
ammunition feeding devices, and to implement the NRC-approved security
plan for IP including the general-licensed ISFSI.
Date of issuance: January 5, 2016.
Effective date: As of its date of issuance and shall be implemented
within 20 days.
Amendment Nos.: Unit 1--58, Unit 2--282, and Unit 3--259. A
publicly-available version is in ADAMS under Package Accession No.
ML14259A209; documents related to these amendments are listed in the
Safety Evaluation enclosed with the amendment.
Facility Operating License Nos. DPR-5, DPR-26, and DPR-64 and
Special Nuclear Materials General-License: The amendments revised the
Facility Operating Licenses including the general-licensed ISFSI.
Date of initial notice in Federal Register: February 27, 2014 (79
FR 11147).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 5, 2016.
No significant hazards consideration comments received: No.
Entergy Nuclear Operations, Inc., Docket No. 50-333, James A.
Fitzpatrick Nuclear Power Plant (Fitzpatrick), and Docket No. 72-12 for
Fitzpatrick Independent Spent Fuel Storage Installation (ISFSI), Oswego
County, New York
Date of application for amendment: August 30, 2013, as supplemented
by letters dated November 12, 2013, May 14, and July 11, 2014, and
January 15, 2015.
Brief description of amendment: The amendment modified the licenses
to reflect a grant of Section 161A of the Atomic Energy Act, to
authorize the licensee the authority to possess and use certain
firearms, ammunition, and other devices such as large-capacity
ammunition feeding devices, and to implement the NRC-approved security
plan for Fitzpatrick including the general-licensed ISFSI.
Date of issuance: January 5, 2016.
Effective date: As of its date of issuance and shall be implemented
within 20 days.
Amendment No.: 310. A publicly-available version is in ADAMS under
package Accession No. v; documents related to this amendment are listed
in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-59 and Special Nuclear
Materials General-License: The amendment revised the Renewed Facility
Operating License including the general-licensed ISFSI.
Date of initial notice in Federal Register: May 6, 2014 (79 FR
25900).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 5, 2016.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point
Nuclear Station (NMP), Unit 2, Oswego County, New York
Date of amendment request: September 3, 2015.
Brief description of amendment: The amendment changed Technical
Specification (TS) Section 2.1.1.2, ``Reactor Core SLs [Safety
Limits],'' to revise the cycle-specific safety limit
[[Page 5503]]
minimum critical power ratio for Cycle 16 for NMP, Unit 2.
Date of issuance: January 5, 2016.
Effective date: As of the date of issuance and shall be implemented
prior to startup from the refueling outage where Global Nuclear Fuel 2
is loaded.
Amendment No.: 153. A publicly-available version is in ADAMS under
Accession No. ML15341A336; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. NPF-69: Amendment revised
the Renewed Facility Operating License and TSs.
Date of initial notice in Federal Register: November 3, 2015 (80 FR
67801).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 5, 2016.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine
Mile Point Nuclear Station, Units 1 and 2 (NMP), and Docket No. 72-1036
for NMP Independent Spent Fuel Storage Installation (ISFSI), Oswego
County, New York
Date of application for amendments: August 14, 2013, as
supplemented by letters dated September 10, 2013, and May 14, 2014.
Brief description of amendments: The amendments modified the
licenses to reflect a grant of Section 161A of the Atomic Energy Act,
to authorize the licensee the authority to possess and use certain
firearms, ammunition, and other devices such as large-capacity
ammunition feeding devices, and to implement the NRC-approved security
plan for NMP including the general-licensed ISFSI.
Date of issuance: January 5, 2016.
Effective date: As of its date of issuance and shall be implemented
within 20 days.
Amendment Nos.: Unit 1--220; Unit 2--154. A publicly-available
version is in ADAMS under Package Accession No. ML14254A450; documents
related to these amendments are listed in the Safety Evaluation
enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-63 and NPF-69, and
Special Nuclear Materials General-License: The amendments revised the
Renewed Facility Operating Licenses including the general-licensed
ISFSI.
Date of initial notice in Federal Register: October 27, 2014 (79 FR
63956).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 5, 2016.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear
Power Plant (Ginna), and Docket No. 72-67 for Ginna Independent Spent
Fuel Storage Installation (ISFSI), Wayne County, New York
Date of application for amendment: August 14, 2013, as supplemented
by letters dated November 4, 2013, and May 14, 2014.
Brief description of amendment: The amendment modified the licenses
to reflect a grant of Section 161A of the Atomic Energy Act, to
authorize the licensee the authority to possess and use certain
firearms, ammunition, and other devices such as large-capacity
ammunition feeding devices, and to implement the NRC-approved security
plan for Ginna including the general-licensed ISFSI.
Date of issuance: January 5, 2016.
Effective date: As of its date of issuance and shall be implemented
within 20 days.
Amendment No.: 120. A publicly-available version is in ADAMS under
Package Accession No. ML14260A140; documents related to this amendment
are listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-18 and Special Nuclear
Materials General-License: The amendment revised the Renewed Facility
Operating License including the general-licensed ISFSI.
Date of initial notice in Federal Register: October 27, 2014 (79 FR
63951).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated January 5, 2016.
No significant hazards consideration comments received: No.
Luminant Generation Company LLC, Docket Nos. 50-445 and 50-446,
Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (CPNPP), Somervell
County, Texas
Date of amendment request: January 28, 2015, as supplemented by
letter dated July 29, 2015.
Brief description of amendments: The amendments revised Technical
Specification (TS) 5.5.16, ``Containment Leakage Rate Testing
Program,'' for CPNPP, to allow an increase in the 10 CFR part 50,
Appendix J, ``Primary Reactor Containment Leakage Testing for Water-
Cooled Power Reactors,'' Type A Integrated Leak Rate Test (ILRT)
interval from a 10-year frequency to a maximum of 15 years and the
extension of the containment isolation valves leakage Type C tests from
its current 60-month frequency to 75 months in accordance with Nuclear
Energy Institute (NEI) 94-01, Revision 3-A, ``Industry Guidance for
Implementing Performance-Based Option of 10 CFR 50, Appendix J,'' July
2012, and conditions and limitations specified in NEI 94-01, Revision
2-A, ``Industry Guidance for Implementing Performance-Based Option of
10 CFR 50, Appendix J,'' October 2008, in addition to limitations and
conditions of NEI 94-01, Revision 3-A. The amendments also deleted the
listing of one-time exceptions previously granted to ILRT frequencies.
Date of issuance: December 30, 2015.
Effective date: As of the date of issuance and shall be implemented
within 120 days from the date of issuance.
Amendment Nos.: Unit 1--165; Unit 2--165. A publicly-available
version is in ADAMS under Accession No. ML15309A073; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Facility Operating License Nos. NPF-87 and NPF-89: The amendments
revised the Facility Operating Licenses and Technical Specifications.
Date of initial notice in Federal Register: March 31, 2015 (80 FR
17092). The supplemental letter dated July 29, 2015, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated December 30, 2015.
No significant hazards consideration comments received: No.
Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo
Canyon Nuclear Power Plant, Unit Nos. 1 and 2, and Docket No. 72-26 for
Diablo Canyon Independent Spent Fuel Storage Installation (ISFSI), San
Luis Obispo County, California
Date of application for amendments: September 24, 2013, as
supplemented by letters dated December 18, 2013, and May 15, 2014.
Brief description of amendments: The amendments modified the
licenses to reflect a grant of Section 161A of the Atomic Energy Act,
to authorize the
[[Page 5504]]
licensee the authority to possess and use certain firearms, ammunition,
and other devices such as large-capacity ammunition feeding devices,
and to implement the NRC-approved security plan for Diablo Canyon Power
Plant and Diablo Canyon ISFSI.
Date of issuance: January 5, 2016.
Effective date: As of its date of issuance and shall be implemented
within 20 days.
Amendment Nos.: Unit 1--222; Unit 2--224, ISFSI-4. A publicly-
available version is in ADAMS under package Accession No. ML15029A249;
documents related to these amendments are listed in the Safety
Evaluation enclosed with the amendments.
Facility Operating License Nos. DPR-80 and DPR-82 and Special
Nuclear Materials License No. SNM-2511: The amendments revised the
Facility Operating Licenses and Special Nuclear Materials License.
Date of initial notice in Federal Register: February 18, 2015 (80
FR 8706).
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 5, 2016.
No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, Docket Nos. 52-027 and 52-028,
Virgil C. Summer Nuclear Station (VCSNS) Units 2 and 3, Fairfield
County, South Carolina
Date of amendment request: September 18, 2014, and supplemented by
letter dated May 28, 2015.
Description of amendment: The amendment authorizes a departure from
VCSNS, Units 2 and 3 plant-specific AP1000 Design Control Document
(DCD) Tier 2* material contained within the VCSNS Units 2 and 3 Updated
Final Safety Analysis Report by relocating fire area rated fire
barriers due to changes to the layout of the switchgear rooms and
office area in the turbine building.
Date of issuance: December 17, 2015.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment No.: 38. A publicly-available version is in ADAMS under
Accession No. ML15313A052; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Facility Combined Licenses No. NPF-93 and NPF-94: Amendment revised
the Facility Combined Licenses.
Date of initial notice in Federal Register: January 6, 2015 (80 FR
526).
The Commission's related evaluation of the amendment is contained
in the Safety Evaluation dated December 17, 2015. The supplemental
letter dated May 28, 2015, 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.
No significant hazards consideration comments received: No.
Southern California Edison Company, et al., Docket Nos. 50-361, 50-362,
and 72-41, San Onofre Nuclear Generating Station, Units 2 and 3, and
Independent Spent Fuel Storage Installation (ISFSI), San Diego County,
California
Date of amendment request: August 28, 2013, as supplemented by
letters dated December 31, 2013, May 15, 2014, and February 10, 2015.
Brief description of amendments: The conforming amendments would
permit the security personnel at San Onofre Nuclear Generating Station
to transfer, receive possess, transport, import, and use certain
firearms and large capacity ammunition feeding devices not previously
permitted to be owned or possessed under NRC authority, notwithstanding
certain local, state, or federal firearms laws, including regulations
that prohibit such actions.
Date of issuance: January 5, 2016.
Effective date: As of its date of issuance and shall be implemented
within 20 days.
Amendment Nos.: Unit 2-232 and Unit 3-225: A publicly-available
version is in ADAMS under Accession No. ML15027A221; documents related
to these amendments are listed in the Safety Evaluation enclosed with
the amendments.
Facility Operating License Nos. NPF-10 and NPF-15: The amendments
revised the Facility Operating Licenses.
Date of initial notice in Federal Register: February 18, 2015 (80
FR 8701). The supplemental letter dated February 10, 2015, provided
additional information that clarified the application, did not expand
the scope of the application as originally noticed, and did not change
the staff's original proposed no significant hazards consideration
determination as published in the Federal Register.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated January 5, 2016.
No significant hazards consideration comments received: Yes,
addressed in Safety Evaluation.
Tennessee Valley Authority (TVA), Docket No. 50-296, Browns Ferry
Nuclear Plant (BFN), Unit 3, Limestone County, Alabama
Date of amendment request: January 27, 2015, as supplemented by
letters dated August 13 and October 23, 2015.
Brief description of amendment: The amendment revised the Technical
Specifications (TSs) for Limiting Condition for Operation (LCO) 3.4.9,
``RCS [Reactor Coolant System] Pressure and Temperature (P/T) Limits.''
The amendment also revised Note 1 of TS Surveillance Requirement
3.4.9.1 to change the vessel pressure from less than 312 pounds per
square inch gauge (psig) to less than 313 psig to conform to the
modified P/T limit curves. The amendment satisfied TVA's commitment to
submit revised BFN, Unit 3, P/T limits prior to the start of the period
of extended operation, as discussed in NRCs Safety Evaluation Report
dated April 2006 (ADAMS Accession No. ML061030032), related to the
license renewal of BFN, Units 1, 2, and 3.
Specifically, the amendment revised the current sets of TS Figures
3.4.9-1, ``Pressure/Temperature Limits for Mechanical Heatup, Cooldown
following Shutdown, and Reactor Critical Operations,'' and 3.4.9-2,
``Pressure/Temperature Limits for Reactor In-Service Leak and
Hydrostatic Testing.'' The amendment replaced the current set valid up
to 20 effective full-power years (EFPYs) with a new set valid up to 38
EFPYs, and replaced the current set valid up to 28 EFPYs with a new set
valid up to 54 EFPYs.
Effective date: As of the date of issuance and shall be implemented
60 days from the date of issuance.
Amendment No.: 278. A publicly available version is in ADAMS under
Accession No. ML15344A321; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-68: Amendment revised
the Renewed Facility Operating License and TSs.
Date of initial notice in Federal Register: May 5, 2015 (80 FR
25720). The supplemental letters dated August 13 and October 23, 2015,
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 January 7, 2016.
[[Page 5505]]
No significant hazards consideration comments received: Yes. The
comment received on Amendment No. 278 is addressed in the Safety
Evaluation dated January 7, 2016.
Dated at Rockville, Maryland, this 21st day of January 2016.
For the Nuclear Regulatory Commission.
Anne T. Boland,
Director, Division of Operating Reactor Licensing, Office of Nuclear
Reactor Regulation.
[FR Doc. 2016-01771 Filed 2-1-16; 8:45 am]
BILLING CODE 7590-01-P