[Federal Register Volume 80, Number 149 (Tuesday, August 4, 2015)]
[Notices]
[Pages 46345-46357]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-18896]
[[Page 46345]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2015-0181]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
AGENCY: Nuclear Regulatory Commission.
ACTION: Biweekly notice.
-----------------------------------------------------------------------
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 July 9, 2015, to July 22, 2015. The last
biweekly notice was published on July 21, 2015.
DATES: Comments must be filed by September 30, 2015. A request for a
hearing must be filed by October 5, 2015.
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-2015-0181. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. For technical questions, contact
the individual listed in the FOR FURTHER INFORMATION CONTACT section of
this document.
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: Lynn Ronewicz, Office of Nuclear
Reactor Regulation, 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-2015-0181 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-2015-0181.
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.
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-2015-0181, 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 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 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 section 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 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 46346]]
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 by the above date, 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 identify 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.
If a hearing is requested, 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.
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
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
ten 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
[[Page 46347]]
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 8:00 a.m. and 8:00 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, MD
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.
Duke Energy Carolinas, LLC, Docket Nos. 50-413 and 50-414, Catawba
Nuclear Station, Units 1 and 2, York County, South Carolina; Docket
Nos. 50-369 and 50-370, McGuire Nuclear Station, Units 1 and 2,
Mecklenburg County, North Carolina
Date of amendment request: June 23, 2015. A publicly-available
version is in ADAMS under Accession No. ML15190A381.
Description of amendment request: The amendments would delete text
from the Technical Specifications that was included to facilitate a
phased implementation of new nuclear instrumentation systems.
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:
Criterion 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 witin the
assumed acceptance limits.
Given the above discussion, it is concluded the proposed
amendment does not significantly increase the probability or
consequences of an accident previously evaluated.
Criterion 2:
Does the proposed amendment create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The LAR proposes administrative non-technical changes only. The
proposed changes will not alter the design requirements of any [SSC]
or its function during accident conditions. No new or different
accidents result from the changes proposed. 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.
[[Page 46348]]
Criterion 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 system 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
safely shutdown the plant and to maintain the plant in a safe
shutdown condition.
Given the above discussion, it is concluded [that] the proposed
amendment does not involve a significant reduction in the margin of
safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 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: Lara S. Nichols, Associate General Counsel,
Duke Energy Corporation, 526 South Church Street--EC07H, Charlotte, NC
28202.
NRC Branch Chief: Robert J. Pascarelli.
Duke Energy Progress, Inc., Docket No. 50-261, H.B. Robinson Steam
Electric Plant Unit No. 2, Darlington County, South Carolina
Date of amendment request: May 13, 2015. A publicly-available
version is in ADAMS under Accession No. ML15133A452.
Description of amendment request: The amendment would revise the
emergency plan by changing the emergency action levels from a scheme
based upon Revision 4 of Nuclear Energy Institute (NEI) 99-01,
``Methodology for Development of Emergency Action Levels,'' to one
based upon Revision 6 of NEI 99-01, ``Development of Emergency Action
Levels for Non-Passive Reactors.'' The NRC formally endorsed NEI 99-01,
Revision 6, in a letter dated March 28, 2013 (ADAMS Accession No.
ML12346A463).
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.
These changes affect the HBRSEP2 [H. B. Robinson Steam Electric
Plant Unit No. 2] Emergency Plan and do not alter any of the
requirements of the Operating License or the Technical
Specifications. The proposed changes do not modify any plant
equipment and do not impact any failure modes that could lead to an
accident. Additionally, the proposed changes do not impact the
consequence of any analyzed accident since the changes do not affect
any equipment related to accident mitigation.
Based on this discussion, the proposed amendment does not
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.
These changes affect the HBRSEP2 Emergency Plan and do not alter
any of the requirements of the Operating License or the Technical
Specifications. They do not modify any plant equipment and there is
no impact on the capability of the existing equipment to perform
their intended functions. No system setpoints are being modified and
no changes are being made to the method in which plant operations
are conducted. No new failure modes are introduced by the proposed
changes. The proposed amendment does not introduce an accident
initiator or malfunctions that would cause a new or different kind
of accident.
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.
These changes affect the HBRSEP2 Emergency Plan and do not alter
any of the requirements of the Operating License or the Technical
Specifications. The proposed changes do not affect any of the
assumptions used in the accident analysis, nor do they affect any
operability requirements for equipment important to plant safety.
Therefore, the proposed changes will not result in a significant
reduction in the margin of safety as defined in the bases for
technical specifications covered in this license amendment request.
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: Lara S. Nichols, Deputy General Counsel,
Duke Energy Corporation, 550 South Tyron Street, Mail Code DEC45A,
Charlotte, NC 28202.
NRC Branch Chief: Shana R. Helton.
Entergy Nuclear Operations, Inc., Docket Nos. 50-003, 50-247, and 50-
286, Indian Point Nuclear Generating, Unit Nos. 1, 2, and 3,
Westchester County, New York
Date of amendment request: June 16, 2015. A publicly available
version is in ADAMS under Accession No. ML15173A070.
Description of amendment request: The amendments would change the
Indian Point Nuclear Generating, Unit Nos. 1, 2, and 3 Cyber Security
Plan (CSP) Milestone 8 full implementation date from June 30, 2016, to
December 31, 2017.
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 CSP Implementation Schedule is
administrative in nature. This change does not alter accident
analysis assumptions, add any initiators, or affect the function of
plant systems or the manner in which systems are operated,
maintained, modified, tested, or inspected. The proposed change does
not require any plant modifications which affect the performance
capability of the structures, systems, and components relied upon to
mitigate the consequences of postulated accidents and has no impact
on the probability or consequences of an accident previously
evaluated.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed change to the CSP Implementation Schedule is
administrative in nature. This proposed change does not alter
accident analysis assumptions, add any initiators, or affect the
function of plant systems or the manner in which systems are
operated, maintained, modified, tested, or inspected. The proposed
change does not require any plant modifications which affect the
performance capability of the structures, systems, and components
relied upon to mitigate the consequences of postulated accidents and
does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
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?
[[Page 46349]]
Response: No.
Plant safety margins are established through limiting conditions
for operation, limiting safety system settings, and safety limits
specified in the technical specifications. The proposed change to
the CSP Implementation Schedule is administrative in nature. In
addition, the milestone date delay for full implementation of the
CSP has no substantive impact because other measures have been taken
which provide adequate protection during this period of time.
Because there is no change to established safety margins as a result
of this change, the proposed change does not involve a significant
reduction in a margin of safety.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Ms. Jeanne Cho, Assistant General Counsel,
Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, NY
10601.
Acting NRC Branch Chief: Michael I. Dudek.
Entergy Nuclear Operations, Inc., Docket No. 50-333, James A.
FitzPatrick Nuclear Power Plant, Oswego County, New York
Date of amendment request: June 22, 2015. A publicly available
version is in ADAMS under Accession No. ML15173A380.
Description of amendment request: The amendment would change the
James A. FitzPatrick Nuclear Power Plant Cyber Security Plan (CSP)
Milestone 8 full implementation date from June 30, 2016, to December
15, 2017.
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 CSP Implementation Schedule is
administrative in nature. This change does not alter accident
analysis assumptions, add any initiators, or affect the function of
plant systems or the manner in which systems are operated,
maintained, modified, tested, or inspected. The proposed change does
not require any plant modifications which affect the performance
capability of the structures, systems, and components relied upon to
mitigate the consequences of postulated accidents and has no impact
on the probability or consequences of an accident previously
evaluated.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed change to the CSP Implementation Schedule is
administrative in nature. This proposed change does not alter
accident analysis assumptions, add any initiators, or affect the
function of plant systems or the manner in which systems are
operated, maintained, modified, tested, or inspected. The proposed
change does not require any plant modifications which affect the
performance capability of the structures, systems, and components
relied upon to mitigate the consequences of postulated accidents and
does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
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.
Plant safety margins are established through limiting conditions
for operation, limiting safety system settings, and safety limits
specified in the technical specifications. The proposed change to
the CSP Implementation Schedule is administrative in nature. In
addition, the milestone date delay for full implementation of the
CSP has no substantive impact because other measures have been taken
which provide adequate protection during this period of time.
Because there is no change to established safety margins as a result
of this change, the proposed change does not involve a significant
reduction in a margin of safety.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Ms. Jeanne Cho, Assistant General Counsel,
Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, NY
10601.
Acting NRC Branch Chief: Michael I. Dudek.
Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear
Plant (PNP), Van Buren County, Michigan
Date of amendment request: June 11, 2015. A publicly-available
version is in ADAMS under Accession No. ML15162A736.
Description of amendment request: The amendment would change the
PNP Cyber Security Plan (CSP) Milestone 8 full implementation date from
the previously approved date of June 30, 2016, to December 15, 2017.
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 CSP implementation schedule is
administrative in nature. This change does not alter accident
analysis assumptions, add any initiators, or affect the function of
plant systems or the manner in which systems are operated,
maintained, modified, tested, or inspected. The proposed change does
not require any plant modifications which affect the performance
capability of the structures, systems, and components relied upon to
mitigate the consequences of postulated accidents, and has no impact
on the probability or consequences of an accident previously
evaluated.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The proposed change to the CSP implementation schedule is
administrative in nature. This proposed change does not alter
accident analysis assumptions, add any initiators, or affect the
function of plant systems or the manner in which systems are
operated, maintained, modified, tested, or inspected. The proposed
change does not require any plant modifications which affect the
performance capability of the structures, systems, and components
relied upon to mitigate the consequences of postulated accidents and
does not create the possibility of a new or different kind of
accident from any accident previously evaluated.
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.
Plant safety margins are established through limiting conditions
for operation,
[[Page 46350]]
limiting safety system settings, and safety limits specified in the
technical specifications. The proposed change to the CSP
implementation schedule is administrative in nature. In addition,
the milestone date delay for full implementation of the CSP has no
substantive impact because other measures have been taken which
provide adequate protection during this period of time. Because
there is no change to established safety margins as a result of this
change, the proposed change does not involve a significant reduction
in a margin of safety.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: Ms. Jeanne Cho, Senior Counsel, Entergy
Services, Inc., 440 Hamilton Ave., White Plains, NY 10601.
NRC Branch Chief: David L. Pelton.
NextEra Energy Seabrook LLC, et al., Docket No. 50-443, Seabrook
Station, Unit No. 1, Rockingham County, New Hampshire
Date of amendment request: July 13, 2015. A publicly-available
version is in ADAMS under Accession No. ML15198A027.
Description of amendment request: The amendment would change the
Technical Specifications (TSs). The proposed change would add a note to
TS Surveillance Requirement (SR) 4.4.1.3.4, which requires verification
that residual heat removal loop operations susceptible to gas
accumulation are sufficiently filled with water in accordance with the
Surveillance Frequency Control Program.
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, along with NRC edits in square brackets, 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.
SR 4.4.1.3.4 verifies RHR [residual heat removal] loop locations
susceptible to gas accumulation are sufficiently filled with water
in accordance with the Surveillance Frequency Control Program. The
proposed change adds a note to allow SR 4.4.1.3.4 to be performed 12
hours after entering the Mode of Applicability. Gas accumulation in
the subject system is not an initiator of any accident previously
evaluated. As a result, the probability of any accident previously
evaluated is not significantly increased. The proposed note does not
change SR 4.4.1.3.4 which ensures that the subject system continues
to be capable of performing its assumed safety function and is not
rendered inoperable due to gas accumulation.
Thus, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any previously evaluated?
Response: No.
The proposed change does not involve a physical alteration of
the plant (i.e., no new or different type of equipment will be
installed) or a change in the methods governing normal plant
operation. In addition, the proposed change does not impose any new
or different requirements that could initiate an accident. The
proposed change does not alter assumptions made in the safety
analysis and is consistent with the safety analysis assumptions.
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
the margin of safety?
Response: No.
The proposed change does not adversely affect any current plant
safety margins or the reliability of the equipment assumed in the
safety analysis. Therefore, there are no changes being made to any
safety analysis assumptions, safety limits, or limiting safety
system settings that would adversely affect plant safety as a result
of the proposed change.
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: William Blair, Managing Attorney--Nuclear,
Florida Power & Light Company, P.O. Box 14000, Juno Beach, FL 33408-
0420.
NRC Branch Chief: Douglas A. Broaddus.
PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear
Generating Station, Unit Nos. 1 and 2, Salem County, New Jersey
Date of amendment request: April 3, 2015, as supplemented by letter
dated June 2, 2015. Publicly-available versions are in ADAMS under
Accession Nos. ML15093A291 and ML15153A193, respectively.
Description of amendment request: The amendments would revise
Technical Specification (TS) 3/4.3.1, ``Reactor Trip System
Instrumentation,'' to support planned plant modifications to replace
the existing source range (SR) and intermediate range (IR) nuclear
instrumentation with a Thermo Scientific Neutron Flux Monitoring
Systems. Specifically, the changes would modify the SR and IR neutron
flux reactor trip Allowable Values and the permissive P-6 reset value,
and would add two new footnotes to the Channel Functional Test and
Channel Calibration in TS 3/4.3.1, Table 4.3-1.
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Do the proposed changes involve a significant increase in the
probability or consequences of an accident previously evaluated?
Response: No.
The Nuclear Instrumentation System (NIS) provides indication and
plant protection through the reactor trip function; it is not an
accident initiator or precursor. The reactor trip is part of the
plant's accident mitigation response. Thus, the probability of an
accident previously evaluated is not significantly increased.
The performance of the replacement SR and IR detectors and
associated equipment will equal or exceed that of the existing
Westinghouse instrumentation. The proposed changes are based on
accepted industry standards and will preserve assumptions in the
applicable accident analyses. The proposed changes do not affect the
integrity of the fission product barriers utilized for the
mitigation of radiological dose consequences as a result of an
accident. The proposed changes do not alter any assumptions
previously made in the radiological consequences evaluations, nor do
they affect mitigation of the radiological consequences of an
accident previously evaluated.
Therefore, the proposed changes do not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Do the proposed changes create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
The manner in which the Reactor Trip System (RTS) provides plant
protection is not changed. The replacement SR and IR detectors and
associated equipment do not affect accident initiation sequences or
response scenarios as modeled in the safety analyses. The SR and IR
detectors and associated equipment are not accident initiators or
precursors. The only physical changes to the plant involve the
replacement detectors and associated equipment. The replacement SR
and IR detectors and
[[Page 46351]]
associated equipment have been designed to applicable regulatory and
industry standards.
No changes to the overall manner in which the plant is operated
are being proposed. Existing accident scenarios remain unchanged and
new or different accident scenarios are not created. The types of
accident defined in the Updated Final Safety Analysis Report (UFSAR)
continue to represent the credible spectrum of events analyzed to
determine safe plant operation.
Therefore, the proposed changes do not create the possibility of
a new or different kind of accident from any previously evaluated.
3. Do the proposed changes involve a significant reduction in a
margin of safety?
Response: No.
Margin of safety is related to the confidence in the ability of
the fission product barriers to perform their intended functions.
These barriers include the fuel cladding, the reactor coolant system
pressure boundary, and the containment. Neither the modification to
replace the SR and IR detectors and associated equipment, nor the
proposed Technical Specification changes will impact these barriers.
Accident mitigating equipment will not be adversely impacted as a
result of the modification. The safety systems credited in the
safety analyses continue to remain available to perform their
required mitigation functions. The proposed changes do not affect
any safety analysis conclusions because the SR and IR neutron flux
reactor trips are not explicitly credited in any accident analyses.
Their functional capability enhances the overall reliability of the
Reactor Protection System.
Therefore, the proposed changes do not involve a significant
reduction in the margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 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: Jeffrie J. Keenan, PSEG Nuclear LLC--N21,
P.O. Box 236, Hancocks Bridge, NJ 08038.
NRC Branch Chief: Douglas A. Broaddus.
III. Previously Published Notices of Consideration of Issuance of
Amendments to Facility Operating Licenses and Combined Licenses,
Proposed No Significant Hazards Consideration Determination, and
Opportunity for a Hearing
The following notices were previously published as separate
individual notices. The notice content was the same as above. They were
published as individual notices either because time did not allow the
Commission to wait for this biweekly notice or because the action
involved exigent circumstances. They are repeated here because the
biweekly notice lists all amendments issued or proposed to be issued
involving no significant hazards consideration.
For details, see the individual notice in the Federal Register on
the day and page cited. This notice does not extend the notice period
of the original notice.
Exelon Generation Company, LLC and PSEG Nuclear LLC, Docket No. 50-278,
Peach Bottom Atomic Power Station (PBAPS), Unit 3, York and Lancaster
Counties, Pennsylvania
Date of amendment request: May 29, 2015. A publicly-available
version is in ADAMS under Accession No. ML15149A473.
Description of amendment request: The amendment would change a
license condition pertaining to the PBAPS, Unit 3, replacement steam
dryer (RSD). Currently, the license condition requires that a revised
analysis for the RSD be submitted to the NRC, as a report, at least 90
days prior to the start of the Unit 3 extended power uprate (EPU)
outage. The proposed amendment would reduce the period before the
outage by which the analysis is to be submitted from 90 days to 30
days. The licensee indicated that the EPU outage is scheduled to start
on September 14, 2015.
Date of publication of individual notice in Federal Register: June
10, 2015 (80 FR 32991).
Expiration date of individual notice: July 10, 2015 (public
comments); August 10, 2015 (hearing requests).
Tennessee Valley Authority, Docket No. 50-390, Watts Bar Nuclear Plant
(WBN), Unit 1, Rhea County, Tennessee
Date of amendment request: June 17, 2015. A publicly-available
version is in ADAMS under Accession No. ML15170A474.
Description of amendment request: The amendment would modify the
technical specifications to define support systems needed in the first
48 hours after a unit shutdown when steam generators are not available
for heat removal. The proposed change is required to support dual unit
operation of WBN (a licensing decision for WBN, Unit 2, is currently
expected to be made in the fall of 2015). The proposed amendment also
requests changes consistent with Technical Specification Task Force-
273-A, Revision 2, ``SFDP [Safety Function Determination Program]
Clarifications,'' to provide clarification related to the requirements
of the SFDP.
Date of publication of individual notice in Federal Register: July
17, 2015 (80 FR 42554).
Expiration date of individual notice: August 16, 2015 (public
comments); September 15, 2015 (hearing requests).
IV. Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses and Final Determination of No Significant Hazards
Consideration and Opportunity for a Hearing. (Exigent Public
Announcement or Emergency Circumstances)
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.
DTE Electric Company, Docket No. 50-341, Fermi 2, Monroe County,
Michigan
Date of amendment request: September 16, 2014, as supplemented by
letter dated April 17, 2015.
Brief description of amendment: The amendment revised the Technical
Specifications (TSs) by relocating
[[Page 46352]]
specific surveillance frequencies to a licensee-controlled program. The
changes are based on NRC-approved TS Task Force (TSTF) Change Traveler
TSTF-425, Revision 3, ``Relocate Surveillance Frequencies to Licensee
Control--RITSTF [Risk-Informed TSTF] Initiative 5b.''
Date of issuance: July 14, 2015.
Effective date: As of the date of issuance and shall be implemented
within 120 days of issuance.
Amendment No.: 201. A publicly-available version is in ADAMS under
Accession No. ML15155B416; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. NPF-43: Amendment revised the
Facility Operating License and TSs.
Date of initial notice in Federal Register: November 12, 2014 (79
FR 67199). The supplemental letter dated April 17, 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 July 14, 2015.
No significant hazards consideration comments received: None.
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: July 25, 2014, as supplemented by
letters dated January 13, 2015, and May 26, 2015.
Brief description of amendments: The amendments changed the
definition in the Technical Specifications (TSs) for RECENTLY
IRRADIATED FUEL. Specifically, the amendments revised requirements
pertaining to secondary containment hatches in order to facilitate
activities performed during refueling outages.
Date of issuance: July 17, 2015.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 298 and 301. A publicly-available version is in
ADAMS under Accession No. ML15162A139; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Renewed Facility Operating License Nos. DPR-44 and DPR-56: The
amendments revised the Facility Operating Licenses and the TSs.
Date of initial notice in Federal Register: September 30, 2014 (79
FR 58816). The supplemental letters dated January 13, 2015, and May 26,
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 July 17, 2015.
No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert
Cliffs Nuclear Power Plant (CCNPP), Unit Nos. 1 and 2, Calvert County,
Maryland
Date of amendment request: September 18, 2014, as supplemented by
letters dated February 17, 2015, and April 2, 2015.
Brief description of amendments: The amendments revised Technical
Specification (TS) 5.5.16, ``Containment Leakage Rate Testing
Program,'' by replacing the reference to Regulatory Guide 1.163
(September 1995) with a reference to Topical Report (TR) Nuclear Energy
Institute (NEI) 94-01, Revision 3-A, and Section 4.1, ``Limitations and
Conditions for NEI TR 94-01, Revision 2,'' of the NRC Safety Evaluation
in NEI 94-01, Revision 2-A, dated October 2008. This reference is the
implementation document to develop 10 CFR part 50, appendix J, Option
B, performance-based primary containment leakage testing program for
CCNPP, Unit Nos. 1 and 2. The changes allow an increase in the Type A
test interval from the current 10 years to a maximum of 15 years, and
allow an increase in the Type C test interval from the current 60
months to 75 months. The change also deletes the one-time exceptions
granted to the Type A test interval and exceptions from the post-
modification Type A test when the steam generators at CCNPP are
replaced.
Date of issuance: July 16, 2015.
Effective date: As of the date of issuance and shall be implemented
within 75 days of issuance.
Amendment Nos.: 310 and 288. A publicly-available version is in
ADAMS under Accession No. ML15154A661; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Renewed Facility Operating License Nos. DPR-53 and DPR-69:
Amendments revised the Renewed Facility Operating Licenses and TSs.
Date of initial notice in Federal Register: November 25, 2014 (79
FR 70214). The supplemental letters dated February 17, 2015, and April
2, 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 July 16, 2015.
No significant hazards consideration comments received: No.
FirstEnergy Nuclear Operating Company, et al., Docket Nos. 50-334 and
50-412, Beaver Valley Power Station, Unit Nos. 1 and 2 (BVPS-1 and 2),
Beaver County, Pennsylvania
Date of amendment request: September 4, 2014, as supplemented by
letter dated December 1, 2014.
Brief description of amendments: The amendments revised the BVPS
Emergency Planning Zone boundary to align it with the boundary that is
currently in use by the emergency management agencies of the three
counties that implement public protective actions around BVPS.
Date of issuance: July 9, 2015.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 294 and 181. A publicly-available version is in
ADAMS under Accession No. ML15131A006; documents related to these
amendments are listed in the Safety Evaluation enclosed with the
amendments.
Facility Operating License Nos. DPR-66 and NPF-73: Amendments
revised the Facility Operating License.
Date of initial notice in Federal Register: October 28, 2014 (79 FR
64224). The supplemental letter dated December 1, 2014, 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 July 9, 2015.
No significant hazards consideration comments received: No.
[[Page 46353]]
Florida Power and Light Company, et al., Docket Nos. 50-335 and 50-389,
St. Lucie Plant, Unit Nos. 1 and 2, St. Lucie County, Florida
Date of amendment request: July 14, 2014, as supplemented by letter
dated June 30, 2015.
Brief description of amendments: The amendments revised the
Technical Specifications (TSs) by modifying or adding surveillance
requirements to verify that system locations susceptible to gas
accumulation are sufficiently filled with water and to provide
allowances that permit performance of the verification. The changes
address NRC Generic Letter 2008-01, ``Managing Gas Accumulation in
Emergency Core Cooling, Decay Heat Removal, and Containment Spray
Systems'' (ADAMS Accession No. ML072910759), as described in Revision 2
of Technical Specification Task Force-523, ``Generic Letter 2008-01,
Managing Gas Accumulation'' (ADAMS Accession No. ML13053A075).
Date of issuance: July 20, 2015.
Effective date: As of the date of issuance and shall be implemented
within 120 days of issuance.
Amendment Nos.: 224 and 174. The amendments are in ADAMS under
Accession No. ML15182A160; documents related to these amendments are
listed in the Safety Evaluation enclosed with the amendments.
Renewed Facility Operating License Nos. DPR-67 and NPF-16:
Amendments revised the TSs.
Date of initial notice in Federal Register: October 28, 2014 (79 FR
64225). The licensee's supplement dated June 30, 2015, did not expand
the scope of the request 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 July 20, 2015.
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: April 9 2014, as supplemented by letters
dated August 29, 2014, and February 20, April 3, and July 7, 2015.
Brief description of amendments: The amendments revised the
Technical Specifications (TSs) by relocating specific surveillance
frequency requirements to a licensee-controlled program with
implementation of Nuclear Energy Institute (NEI) 04-10, ``Risk Informed
Technical Specification Initiative 5b, Risk Informed Method for Control
of Surveillance Frequencies'' (ADAMS Accession No. ML071360456). The
NEI 04-10 methodology provides reasonable acceptance guidelines and
methods for evaluating the risk increase of proposed changes to
surveillance frequencies, consistent with Regulatory Guide 1.177, ``An
Approach for Plant-Specific Risk-Informed Decisionmaking: Technical
Specifications'' (ADAMS Accession No. ML003740176). The changes are
consistent with NRC-approved Technical Specification Task Force (TSTF)
Standard Technical Specifications Change TSTF-425, ``Relocate
Surveillance Frequencies to Licensee Control--RITSTF [Risk Informed
Technical Specifications Task Force] Initiative 5b,'' Revision 3 (ADAMS
Accession No. ML090850642). The Federal Register notice published on
July 6, 2009 (74 FR 31996), announced the availability of TSTF-425,
Revision 3. The amendments also include editorial changes to the TSs,
administrative deviations from TSTF-425, and other changes resulting
from differences between the licensee's TSs and the TSs on which TSTF-
425 was based.
Date of issuance: July 16, 2015.
Effective date: As of the date of issuance and shall be implemented
within 90 days of issuance.
Amendment Nos.: 263 and 258. The amendments are in ADAMS under
Accession No. ML15166A320; 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:
Amendments revised the Facility Operating License and TSs.
Date of initial notice in Federal Register: The NRC staff initially
made a proposed determination that the amendment request dated April 9,
2014, involved no significant hazards consideration (NSHC) (July 22,
2014, 79 FR 44551). By letters dated August 29, 2014, and February 20,
2015, the licensee provided clarifying information that did not expand
the scope of the application and did not change the NRC staff's
original proposed NSHC determination, as published in the Federal
Register on July 22, 2014 (79 FR 44551). Subsequently, by letter dated
April 3, 2015, the licensee supplemented its amendment request with a
proposed change that expanded the scope of the request. Therefore, the
NRC published a second proposed NSHC determination in the Federal
Register on May 12, 2015 (80 FR 27199), which superseded the notice
dated July 22, 2014 (79 FR 44551). The licensee's supplement dated July
7, 2015, did not expand the scope of the request and did not change the
staff's proposed NSHC determination that was published in the Federal
Register on May 12, 2015 (80 FR 27199).
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated July 16, 2015.
No significant hazards consideration comments received: No.
Nebraska Public Power District, Docket No. 50-298, Cooper Nuclear
Station, Nemaha County, Nebraska
Date of amendment request: July 17, 2014, as supplemented by letter
dated February 19, 2015.
Brief description of amendment: The amendment moved the Linear Heat
Generation Rate (LHGR) and Single Loop Operation LHGR limits from the
Technical Requirements Manual to the Technical Specifications (TSs).
Accordingly, the amendment added TS 3.2.3, ``Linear Heat Generation
Rate (LHGR),'' and modified TS 1.1, ``Definitions''; TS 3.4.1,
``Recirculation Loops Operating''; TS 3.7.7, ``The Main Turbine Bypass
System''; and TS 5.6.5, ``Core Operating Limits Report (COLR).''
Date of issuance: July 14, 2015.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No.: 251. A publicly-available version is in ADAMS under
Accession No. ML15168A171; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-46: Amendment revised
the Facility Operating License and TSs.
Date of initial notice in Federal Register: September 30, 2014 (79
FR 58820). The supplemental letter dated February 19, 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 July 14, 2015.
No significant hazards consideration comments received: No.
[[Page 46354]]
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 18, 2014, as supplemented by letter
dated November 7, 2015.
Brief description of amendment: The amendment changed the Cyber
Security Plan for Point Beach Nuclear Plants, Units 1 and 2, by
revising the completion date of Milestone 8 of the Cyber Security Plan
Implementation schedule.
Date of issuance: July 14, 2015.
Effective date: These amendments will be effective as of their date
of issuance.
Amendment Nos.: 252 and 256. A publicly-available version is in
ADAMS under Accession No. ML15155A539; 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:
Amendments revised the Facility Operating License and Technical
Specifications.
Date of initial notice in Federal Register: January 6, 2015 (80 FR
536). The supplemental letter dated November 7, 2014, 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 July 14, 2015.
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: July 24, 2014, as supplemented by two
letters dated December 11, 2014, and a letter dated June 30, 2015.
Brief description of amendment: The amendment revised Seabrook
Station Technical Specification (TS) 3.3.3.1, ``Radiation Monitoring
for Plant Operations,'' to eliminate duplicate requirements, resolve an
inconsistency, and correct a deficiency.
Date of issuance: July 17, 2015.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No.: 149. A publicly-available version is in ADAMS under
Accession No. ML15096A131; documents related to this amendment are
listed in the Safety Evaluation enclosed with the amendment.
Facility Operating License No. NPF-86: Amendment revised the
Facility Operating License and Technical Specifications.
Date of initial notice in Federal Register: September 30, 2014 (79
FR 58821). The supplemental letters dated December 11, 2014, and June
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 amendment is contained
in a Safety Evaluation dated July 17, 2015.
No significant hazards consideration comments received: No.
Southern California Edison Company, et al., Docket Nos. 50-361 and 50-
362, San Onofre Nuclear Generating Station (SONGS), Units 2 and 3, San
Diego County, California
Date of amendment request: March 21, 2014, as supplemented by
letters dated October 1, 2014; and February 23, February 25, and March
18, 2015.
Brief description of amendment: The amendments revised the SONGS,
Units 2 and 3, Facility Operating Licenses and associated Technical
Specifications (TSs) to conform to the permanent shutdown and defueled
status of these facilities.
Date of issuance: July 17, 2015.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment Nos.: 230 and 223. A publicly-available version is in
ADAMS under Accession No. ML15139A390; 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 and TSs.
Date of initial notice in Federal Register: September 16, 2014 (79
FR 55513). The supplemental letters dated October 1, 2014; and February
23, February 25, 2015, and March 18, 2015, 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 July 17, 2015.
No significant hazards consideration comments received: No.
V. Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses and Final Determination of No Significant Hazards
Consideration and Opportunity for a Hearing. (Exigent Public
Announcement or Emergency Circumstances)
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 for the
amendment 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.
Because of exigent or emergency circumstances associated with the
date the amendment was needed, there was not time for the Commission to
publish, for public comment before issuance, its usual notice of
consideration of issuance of amendment, proposed no significant hazards
consideration determination, and opportunity for a hearing.
For exigent circumstances, the Commission has either issued a
Federal Register notice providing opportunity for public comment or has
used local media to provide notice to the public in the area
surrounding a licensee's facility of the licensee's application and of
the Commission's proposed determination of no significant hazards
consideration. The Commission has provided a reasonable opportunity for
the public to comment, using its best efforts to make available to the
public means of communication for the public to respond quickly, and in
the case of telephone comments, the comments have been recorded or
transcribed as appropriate and the licensee has been informed of the
public comments.
In circumstances where failure to act in a timely way would have
resulted, for example, in derating or shutdown of a nuclear power plant
or in prevention of either resumption of operation or of increase in
power output up to the plant's licensed power level, the Commission may
not have had an opportunity to provide for public comment on its no
significant hazards consideration determination. In such case, the
license amendment has been issued without opportunity for
[[Page 46355]]
comment. If there has been some time for public comment but less than
30 days, the Commission may provide an opportunity for public comment.
If comments have been requested, it is so stated. In either event, the
State has been consulted by telephone whenever possible.
Under its regulations, the Commission may issue and make an
amendment immediately effective, notwithstanding the pendency before it
of a request for a hearing from any person, in advance of the holding
and completion of any required hearing, where it has determined that no
significant hazards consideration is involved.
The Commission has applied the standards of 10 CFR 50.92 and has
made a final determination that the amendment involves no significant
hazards consideration. The basis for this determination is contained in
the documents related to this action. Accordingly, the amendments have
been issued and made effective 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 51.12(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
application for amendment, (2) the amendment to Facility Operating
License or Combined License, as applicable, 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.
A. Opportunity To Request a Hearing and Petition for Leave to Intervene
The Commission is also offering an opportunity for a hearing with
respect to the issuance of the amendment. 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, and electronically on the Internet at the NRC's Web
site, http://www.nrc.gov/reading-rm/doc-collections/cfr/. If there are
problems in accessing the document, contact the PDR's Reference staff
at 1-800-397-4209, 301-415-4737, or by email to [email protected].
If a request for a hearing or petition for leave to intervene is filed
by the above date, 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 identify 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 petitioner
intends to rely in proving the contention at the hearing. The
petitioner must also provide references to those specific sources and
documents of which the petitioner is aware and on which the 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 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. Since the Commission has made a final determination that the
amendment involves no significant hazards consideration, if a hearing
is requested, it will not stay the effectiveness of the amendment. Any
hearing held would take place while the amendment is in effect.
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
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
ten 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
[[Page 46356]]
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 8:00 a.m. and 8:00 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, MD
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.
Indiana Michigan Power Company, Docket No. 50-315, Donald C. Cook
Nuclear Plant, Unit 1, Berrien County, Michigan
Date of amendment request: June 29, 2015, as supplemented by letter
dated July 2, 2015.
Brief description of amendment: The amendment revised Technical
Specification (TS) 3.3.2, ``Engineered Safety Feature Actuation System
(ESFAS) Instrumentation,'' by adding a new condition for one or more
inoperable required channels for main feedwater pump trips, changing
Table 3.3.2-1 to add a footnote to the Applicable Mode Column for Mode
2 and to reflect the new Condition, and renumbering existing
Conditions.
Date of issuance: July 10, 2015.
Effective date: As of the date of issuance and shall be implemented
within 30 days of issuance.
Amendment No.: 328. A publicly-available version is in ADAMS under
Accession No. ML15187A002; documents related to the amendment are
listed in the Safety Evaluation enclosed with the amendment.
Renewed Facility Operating License No. DPR-58: Amendment revised
the Renewed Facility Operating License and TSs.
Public comments requested as to proposed no significant hazards
consideration (NSHC): Yes. Public
[[Page 46357]]
notice of the proposed amendment was published in The Herald-Palladium,
located in the City of St. Joseph, Berrien County, Michigan, on July 3
and July 4, 2015. The notice provided an opportunity to submit comments
on the Commission's proposed NSHC determination. No comments were
received.
The Commission's related evaluation of the amendment, finding of
exigent circumstances, State consultation, public comments, and final
NSHC determination are contained in a Safety Evaluation dated July 10,
2015.
Attorney for licensee: Robert B. Haemer, Senior Nuclear Counsel,
One Cook Place, Bridgman, MI 49106.
NRC Branch Chief: David L. Pelton.
Dated at Rockville, Maryland, this 27th day of July, 2015.
For the Nuclear Regulatory Commission.
George A. Wilson, Jr.,
Deputy Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2015-18896 Filed 8-3-15; 8:45 am]
BILLING CODE 7590-01-P