Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 79617-79625 [2015-31754]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 80, Number 245 (Tuesday, December 22, 2015)]
[Notices]
[Pages 79617-79625]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2015-31754]


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NUCLEAR REGULATORY COMMISSION

[NRC-2015-0276]


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 November 24, 2015, to December 7, 2015. The 
last biweekly notice was published on December 8, 2015.

DATES: Comments must be filed by January 21, 2016. A request for a 
hearing must be filed February 22, 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 https://www.regulations.gov and search for Docket ID NRC-2015-0276. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: Carol.Gallagher@nrc.gov.
     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: Lynn.Ronewicz@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0276 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 https://www.regulations.gov and search for Docket ID NRC-2015-0276.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://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 pdr.resource@nrc.gov. 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-2015-0276, 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 https://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

[[Page 79618]]

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.

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 https://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 
February 22, 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

[[Page 79619]]

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 
February 22, 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 
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 hearing.docket@nrc.gov, 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 https://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 https://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 https://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 https://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 https://www.nrc.gov/site-help/e-submittals.html, by email to 
MSHD.Resource@nrc.gov, 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 
https://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

[[Page 79620]]

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.

FirstEnergy Nuclear Operating Company, Docket No. 50-440, Perry Nuclear 
Power Plant (PNPP), Unit No. 1, Lake County, Ohio

    Date of amendment request: October 29. 2015. A publicly-available 
version is in ADAMS under Accession No. ML15316A508.
    Description of amendment request: The proposed amendment would 
revise the emergency action level scheme to be based on the Nuclear 
Energy Institute (NEI) guidance in NEI 99-01, ``Development of 
Emergency Action Levels for Non-Passive Reactors,'' Revision 6.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendment affects the PNPP EP [Emergency Plan] and 
associated EALs [Emergency Action Level]; it does not alter the 
Operating License or the Technical Specifications. The proposed 
amendment does not change the design function of any system, 
structure, or component and does not change the way the plant is 
maintained or operated. The proposed amendment does not affect any 
accident mitigating feature or increase the likelihood of 
malfunction for plant structures, systems, and components.
    The proposed amendment will not change any of the analyses 
associated with the PNPP Updated Safety Analysis Report Chapter 15 
accidents because plant operation, structures, systems, components, 
accident initiators, and accident mitigation functions remain 
unchanged.
    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 affects the PNPP EP and associated EALs; 
it does not alter the Operating License or the Technical 
Specifications. The proposed amendment does not change the design 
function of any system, structure, or component and does not change 
the way the plant is operated or maintained. The proposed amendment 
does not create a credible failure mechanism, malfunction, or 
accident initiator not already considered in the design and 
licensing basis.
    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.
    Safety margins are applied to design and licensing basis 
functions and to the controlling values of parameters to account for 
various uncertainties and to avoid exceeding regulatory or licensing 
limits. The proposed amendment affects the PNPP EP and associated 
EALs; it does not alter the Operating License or the Technical 
Specifications. The proposed amendment does not involve a physical 
change to the plant and does not change methods of plant operation 
within prescribed limits, and does not affect design and licensing 
basis functions or controlling values of parameters for plant 
systems, structures, and components.
    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: David W. Jenkins, Attorney, FirstEnergy 
Corporation, Mail Stop A-GO-15, 76 South Main Street, Akron, OH 44308.
    NRC Branch Chief: David L. Pelton.

Florida Power & Light Company, Docket Nos. 50-250 and 50-251, Turkey 
Point Nuclear Generating, Unit Nos. 3 and 4, Miami-Dade County, Florida

    Date of amendment request: October 12, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15300A264.
    Description of amendment request: The amendment would revise the 
qualification requirements for licensed operators in the technical 
specifications for Turkey Point Nuclear Generating, Unit Nos. 3 and 4.
    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 change is of an administrative nature and does not 
impact the physical configuration or function of plant structures, 
systems, or components (SSCs) or the manner in which SSCs are 
operated, maintained, modified, tested, or inspected. No actual 
facility equipment or accident analyses are affected by the proposed 
changes. Although licensed operator qualifications and training may 
have an indirect impact on accidents previously evaluated, the 
proposed change does not reduce any operator qualification or 
training requirements.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed change does not involve a physical alteration of 
the plant (no new or different type of equipment will be installed). 
The proposed change does not create any new failure modes for 
existing equipment or any new limiting single failures. 
Additionally, the proposed change does not involve a change in the 
methods governing normal plant operation and all safety functions 
will continue to perform as previously assumed in accident analyses. 
Thus, the proposed change does not adversely affect the design 
function or operation of any SSCs important to safety.
    No new accident scenarios, failure mechanisms, or limiting 
single failures are introduced as a result of the proposed change. 
The proposed change does not challenge the performance or integrity 
of any safety-related system.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any previously 
evaluated.

[[Page 79621]]

    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The margin of safety associated with the acceptance criteria of 
any accident is unchanged. The proposed change will have no effect 
on the availability, operability, or performance of safety-related 
systems and components. The proposed change will not adversely 
affect the operation of plant equipment or the function of equipment 
assumed in the accident analysis.
    The proposed change does not change or lessen the qualification 
requirements for licensed operators. One purpose of the 1987 rule 
change (Operators' Licenses and Conforming Amendments) was to 
improve the safety of nuclear power plant operations by improving 
the operator licensing process and examination content. The NRC 
reviewed the licensed operator training program experience 
guidelines in effect at the time of the 1987 rule change and 
determined that they were equivalent to the baseline experience 
criteria of Regulatory Guide 1.8, Revision 2, which was issued in 
conjunction with the rule change. The proposed change maintains 
licensed operator training and qualification requirements consistent 
with 10 CFR 55 and ensures properly qualified licensed operators 
operate the facility.
    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 S. Blair, Managing Attorney--
Nuclear, Florida Power & Light Company, 700 Universe Blvd., MS LAW/JB, 
Juno Beach, FL 33408-0420.
    NRC Branch Chief: Benjamin G. Beasley.

Indiana Michigan Power Company, Docket No. 50-316, Donald C. Cook 
Nuclear Plant, Unit 2, Berrien County, Michigan

    Date of amendment request: October 19, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15293A497.
    Description of amendment request: The proposed amendment would 
modify technical specifications (TSs) requirements for the Engineered 
Safety Feature Actuation System Instrumentation by adding a new 
Condition for inoperable required channels for main feedwater (MFW) 
pump trips, and by adding a footnote to the Applicable Mode column of 
TS Table 3.3.2-1 to reflect the new 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 design basis events which impose initiation of the AFW 
[auxiliary feedwater] System requirements are loss of normal MFW, 
main steamline break, LOOP [loss of offsite power], and SBLOCA 
[small break loss-of-coolant accident]. These design bases event 
evaluations assume actuation of the AFW System due to LOOP signal, 
SG [steam generator] water level--low-low or a safety injection 
signal. The anticipatory motor driven AFW pump autostart signals 
from the MFW pumps are not credited in any DBAs [design basis 
accidents] and are, therefore, not part of the primary success path 
for postulated accident mitigation, as defined by 10 CFR 
50.36(c)(2)(ii), Criterion 3. Modifying Completion Time clock 
activation requirements, providing a Condition and Required Actions 
for more than one inoperable channel for this function, and 
modifying Modes 1 and 2 Applicability for this function will not 
impact any previously evaluated design basis accidents.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    This TS change allows for one or more MFW pump channels to be 
inoperable during Modes 1 and 2 and has an operational allowance 
during Modes 1 and 2 for placing MFW pumps in service or securing 
MFW pumps. This change involves an anticipatory AFW auto-start 
function that is not credited in the accident analysis. Since this 
change only affects the conditions at which this auto-start function 
needs to be operable and does not affect the function that actuates 
AFW due to LOOP, low-low steam generator level or a safety injection 
signal, it will not be an initiator to a new or different kind of 
accident from any accident previously evaluated.
    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.
    This TS change involves the automatic start of the AFW pumps due 
to trip of both MFW pumps, which is not an assumed start signal for 
design basis events. This change does not modify any values or 
limits involved in a safety related function or accident analysis.
    Therefore, the proposed amendment does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the 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: Robert B. Haemer, Senior Nuclear Counsel, 
One Cook Place, Bridgman, MI 49106.
    NRC Branch Chief: David L. Pelton.

NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold 
Energy Center, Linn County, Iowa

    Date of amendment request: October 14, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15289A233.
    Description of amendment request: The amendment would replace 
references to Section XI of the American Society of Mechanical 
Engineers (ASME) Boiler and Pressure Vessel Code with reference to the 
ASME Code of Operation and Maintenance (OM Code) of Nuclear Power 
Plants in Technical Specification (TS) Section 5.5.6 for the Inservice 
Testing (IST) Program. In addition to the replacement of the 
references, it would also add a provision in TS Section 5.5.6 to only 
apply the extension allowance of Surveillance Requirement 3.0.2 to the 
frequency table listed in the TS as part of the IST Program and to 
normal and accelerated inservice testing frequencies of 2 years or 
less, as applicable.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes revise TS Section 5.5.6 to conform to the 
requirements of 10 CFR 50.55a, ``Codes and standards,'' paragraph 
(f) regarding the inservice testing of pumps and valves. TS Section 
5.5.6 currently references the ASME Boiler and Pressure Vessel Code, 
Section XI, requirements for the inservice testing of ASME Code 
Class 1, 2, and 3 pumps and valves. The proposed changes would 
reference the ASME OM Code as applicable, which is consistent with 
10 CFR 50.55a, paragraph (f), ``Inservice testing requirements.'' In 
addition, the proposed changes clarify that the extension allowance 
of SR 3.0.2 only applies to the frequency table listed in the TS, if 
applicable, as part of the Inservice Testing Program and to normal 
and accelerated inservice testing frequencies of two years or less. 
The

[[Page 79622]]

definitions of the frequencies are not changed by the requested 
amendment.
    The proposed changes are administrative in nature, do not affect 
any accident initiators, do not affect the ability to successfully 
respond to previously evaluated accidents and do not affect 
radiological assumptions used in the evaluations. Thus, the 
probability or radiological consequences of any accident previously 
evaluated are not increased.
    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 revise TS Section 5.5.6 to conform to the 
requirements of 10 CFR 50.55a(f) regarding the inservice testing of 
pumps and valves. TS Section 5.5.6 currently references the ASME 
Boiler and Pressure Vessel Code, Section XI, requirements for the 
inservice testing of ASME Code Class 1, 2, and 3 pumps and valves. 
The proposed changes would reference the ASME OM Code as applicable, 
which is consistent with 10 CFR 50.55a(f). In addition, the proposed 
changes clarify that the extension allowance of SR 3.0.2 only 
applies to the frequency table listed in the TS, if applicable, as 
part of the Inservice Testing Program and to normal and accelerated 
inservice testing frequencies of two years or less. The definitions 
of the frequencies are not changed by the requested amendment.
    The proposed changes to TS Section 5.5.6 do not affect the 
performance of any structure, system, or component credited with 
mitigating any accident previously evaluated and do not introduce 
any new modes of system operation or failure mechanisms.
    Therefore, the proposed changes do 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.
    Margin of safety is related to confidence in the ability of the 
fission product barriers (fuel cladding, reactor coolant system, and 
primary containment) to perform their design functions during and 
following postulated accidents. The proposed changes do not affect 
the function of the reactor coolant pressure boundary or its 
response during plant transients. The proposed changes revise TS 
Section 5.5.6 to conform to the requirements of 10 CFR 50.55a(f) 
regarding the inservice testing of pumps and valves.
    TS Section 5.5.6 currently references the ASME Boiler and 
Pressure Vessel Code, Section XI, requirements for the inservice 
testing of ASME Code Class 1, 2, and 3 pumps and valves. The 
proposed changes would reference the ASME OM Code as applicable, 
which is consistent with 10 CFR 50.55a(f). In addition, the proposed 
changes clarify that the extension allowance of Surveillance 
Requirement (SR) 3.0.2 only applies to the frequency table listed in 
the TS, if applicable, as part of the Inservice Testing Program and 
to normal and accelerated inservice testing frequencies of two years 
or less. The definitions of the frequencies are not changed by the 
requested amendment.
    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 this change. The proposed change will not result 
in plant operation in a configuration outside the design basis. The 
proposed change does not adversely affect systems that respond to 
safely shutdown the plant and to maintain the plant in a safe 
shutdown condition.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Mr. William Blair, Florida Power & Light 
Company, P.O. Box 14000, Juno Beach, FL 33408-0420.
    NRC Branch Chief: David L. Pelton.

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.

Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power 
Station, Unit No. 3 (MPS3), New London County, Connecticut

    Date of amendment request: May 8, 2014, as supplemented by letters 
dated August 14, October 15, and October 16, 2014, and May 18 and July 
27, 2015.
    Brief description of amendment: The amendment revised the MPS3 
Technical Specification (TS) 3/4.3.1, ``Reactor Trip System 
Instrumentation,'' and TS 3/4.3.2, ``Engineered Safety Features 
Actuation System [ESFAS] Instrumentation,'' to adopt the Completion 
Time (CT) and bypass test time changes in NRC approved Westinghouse 
Electric Company LLC's Topical Reports WCAP-14333-P-A, Revision 1, 
``Probabilistic Risk Analysis of the RPS [Reactor Protection System] 
and ESFAS Test Times and Completion Times,'' October 1998, and WCAP-
15376-P-A, Revision 1, ``Risk-Informed Assessment of the RTS [Reactor 
Trip System] and ESFAS Surveillance Test Intervals and Reactor Trip 
Breaker Test and Completion Times,'' March 2003. The amendment extended 
the CTs and bypass test times for several required actions in TS 3/
4.3.1 and TS 3/4.3.2.
    Date of issuance: November 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 266. A publicly-available version is in ADAMS under 
Accession No. ML15288A004; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-49: Amendment revised 
the Renewed Facility Operating License and TSs.
    Date of initial notice in Federal Register: December 23, 2014 (79 
FR 77044). The supplemental letters dated May 18 and July 27, 2015, 
provided additional information that clarified the application, did not 
expand the scope of

[[Page 79623]]

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 November 30, 2015.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455, 
Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois

    Date of amendment request: November 24, 2014.
    Brief description of amendments: The amendments revised Condition I 
and Surveillance Requirement 3.7.9.3 associated with Technical 
Specification (TS) Section 3.7.9, ``Ultimate Heat Sink (UHS).'' The 
changes reflect the current design basis flood level and ensure the 
operability of the service water makeup pumps to meet TS, Section 3.7.9 
limiting condition for operation requirement.
    Date of issuance: November 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment Nos.: 193. A publicly-available version is in ADAMS under 
Accession No. ML15280A297; documents related to these amendments are 
listed in the Safety Evaluation enclosed with the amendments.
    Renewed Facility Operating License Nos. NPF-37 and NPF-66: 
Amendments revised the TSs and Renewed Facility Operating License.
    Date of initial notice in Federal Register: March 31, 2015 (80 FR 
17088).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated November 30, 2015.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point 
Nuclear Station, Unit 2, Oswego County, New York

    Date of amendment request: November 19, 2014, as supplemented by 
letters dated July 10, 2015; September 10, 2015; and September 24, 
2015.
    Brief description of amendment: The amendment revised the technical 
specifications (TSs) to require that changes to specific surveillance 
frequencies will be made in accordance with Nuclear Energy Institute 
04-10, Revision 1, ``Risk-Informed Technical Specifications Initiative 
5b, Risk-Informed Method for Control of Surveillance Frequencies'' 
(ADAMS Accession No. ML071360456). The change is the adoption of NRC-
approved Technical Specification Task Force (TSTF) Standard Technical 
Specifications Change Traveler TSTF-425, Revision 3, ``Relocate 
Surveillance Frequencies to Licensee Control--RITSTF [Risk-Informed 
TSTF] Initiative 5b'' (ADAMS Accession No. ML090850642). The Federal 
Register notice published on July 6, 2009 (74 FR 31996), announced the 
availability of TSTF-425, Revision 3.
    Date of issuance: November 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days of issuance.
    Amendment No.: 152. A publicly-available version is in ADAMS under 
Accession No. ML15317A307; 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: March 17, 2015 (80 FR 
13906). The supplemental letters dated July 10, 2015; September 10, 
2015; and September 24, 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 November 30, 2015.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear 
Power Plant, Wayne County, New York

    Date of amendment request: March 28, 2013, as supplemented by 
letters dated December 17, 2013; January 29, February 28, September 5, 
September 24, and December 4, 2014; and March 18, June 11, and August 
7, 2015.
    Brief description of amendment: The amendment adopted a new risk-
informed performance-based fire protection licensing basis, which 
complies with the requirements in 10 CFR Sections 50.48(a) and 
50.48(c), the guidance in Regulatory Guide 1.205, ``Risk-Informed 
Performance-Based Fire Protection for Existing Light-Water Nuclear 
Power Plants,'' Revision 1, and National Fire Protection Association 
805, ``Performance-Based Standard for Fire Protection for Light Water 
Reactor Electric Generating Plants,'' 2001 Edition. The amendment also 
follows the guidance in Nuclear Energy Institute 04-02, ``Guidance for 
Implementing a Risk-Informed, Performance-Based Fire Protection Program 
Under 10 CFR 50.48(c),'' Revision 2.
    Date of issuance: November 23, 2015.
    Effective date: As of the date of issuance to be implemented as 
described in the transition license conditions.
    Amendment No.: 119. A publicly-available version is in ADAMS under 
Accession No. ML15271A101; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-18: Amendment revised 
the Renewed Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: November 4, 2014 (79 FR 
65430). The supplemental letters dated December 17, 2013; January 29, 
February 28, September 5, September 24, and December 4, 2014; and March 
18, June 11, and August 7, 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 November 23, 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, Beaver County, 
Pennsylvania

    Date of amendment request: March 19, 2015, as supplemented by 
letter dated May 6, 2015.
    Brief description of amendments: The amendment request contained 
sensitive unclassified non-safeguards information (SUNSI). The 
amendment changed the Beaver Valley Power Station, Unit Nos. 1 and 2, 
Facility Operating Licenses. Specifically, the license amendments 
revised the Cyber Security Plan Milestone 8 full implementation date as 
set forth in the cyber security plan implementation schedule.
    Date of issuance: December 1, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 295 (Unit 1) and 183 (Unit 2). A publicly-available

[[Page 79624]]

version is in ADAMS under Accession No. ML15302A433; 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 Licenses.
    Date of initial notice in Federal Register: July 7, 2015 (80 FR 
38774).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 1, 2015.
    No significant hazards consideration comments received: No.

Indiana Michigan Power Company, Docket No. 50-315, Donald C. Cook 
Nuclear Plant, Unit 1, Berrien County, Michigan

    Date of amendment request: October 8, 2013, as supplemented by 
letters dated April 29, 2014; June 5, 2014; July 3, 2014; September 30, 
2014; and September 18, 2015.
    Brief description of amendment: The amendment increased the normal 
reactor coolant system temperature and pressure at the Donald C. Cook 
Nuclear Plant, Unit 1, consistent with previously licensed conditions. 
The amendment modified the Unit 1 technical specifications (TSs) and 
licensing basis associated with this change.
    Date of issuance: November 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 180 days from the date of issuance.
    Amendment No.: 329. A publicly-available version is in ADAMS under 
Accession No. ML14197A097; documents related to this 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.
    Date of initial notice in Federal Register: February 19, 2014 (79 
FR 9495). The supplemental letters dated April 29, 2014; June 5, 2014; 
July 3, 2014; September 30, 2014; and September 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 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 November 30, 2015.
    No significant hazards consideration comments received: No.

NextEra Energy, Point Beach, LLC, Docket Nos. 50-266 and 50-301, Point 
Beach Nuclear Plant, Units 1 and 2, Town of Two Rivers, Manitowoc 
County, Wisconsin

    Date amendment request: March 27, 2015.
    Brief description of amendments: The amendments incorporated the 
guidance of Technical Specification Task Force Traveler (TSTF)-510, 
Revision 2, ``Revision to Steam Generator Program Inspection 
Frequencies and Tube Sample Selection.'' The guidance in TSTF-510 
revises TS 3.4.17, ``Steam Generator (SG) Tube Integrity''; TS 5.5.8, 
``Steam Generator (SG) Program''; and TS 5.6.8, ``Steam Generator Tube 
Inspection Report.''
    Date of issuance: November 25, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 254 (Unit 1) and 258 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML15293A457; 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: June 9, 2015 (80 FR 
32627).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated November 25, 2015.
    No significant hazards consideration comments received: No.

Northern States Power Company--Minnesota, Docket Nos. 50-282 and 50-
306, Prairie Island Nuclear Generating Plant, Units 1 and 2, Goodhue 
County, Minnesota

    Date of amendment request: December 11, 2014.
    Brief description of amendments: The amendments revised Technical 
Specification (TS) 3.3.3, ``Event Monitoring (EM) Instrumentation,'' to 
add steam generator water level--narrow range instruments to Table 
3.3.3-1, and to revise Appendix B, Additional Conditions, of the 
Renewed Facility Operating Licenses to support Alternate Source Term 
implementation at the Prairie Island Nuclear Plant, Units 1 and 2.
    Date of issuance: November 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment Nos.: 216 (Unit 1) and 204 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML15264A209; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-42 and DPR-60: 
Amendments revised the Renewed Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: April 14, 2015 (80 FR 
20023).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated November 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 (DCPP), Units 1 and 2, San Luis Obispo 
County, California

    Date of application for amendments: October 2, 2014.
    Brief description of amendments: The amendments consisted of 
changes to the licensing basis as described in DCPP Updated Final 
Safety Analysis Report (UFSAR) Sections 3.6.2.1.1.1, ``Reactor Coolant 
System Main Loop Piping (Leak-Before-Break),'' and 4.2.1.1.2, ``Fuel 
Assembly Structure.'' The amendments revised the UFSAR to document that 
the fuel assembly structural analyses are based on a pipe break 
location that considers the application of leak-before-break and the 
results of the fuel assembly structural analyses are used as an input 
to demonstrate compliance with 10 CFR 50.46(b)(4).
    Date of issuance: December 3, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days from the date of issuance.
    Amendment Nos.: 221 (Unit 1) and 223 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML15281A164; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Facility Operating License Nos. DPR-80 and DPR-82: The amendments 
revised the Facility Operating Licenses.
    Date of initial notice in Federal Register: March 3, 2015 (80 FR 
11496).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated December 3, 2015.
    No significant hazards consideration comments received: No.

[[Page 79625]]

PSEG Nuclear LLC, Docket No. 50-354, Hope Creek Generating Station, 
Salem County, New Jersey

    Date of amendment request: November 25, 2014.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) Surveillance Requirement 4.7.2.1.1.b to reduce the 
required run time of the control room emergency filtration subsystems, 
with heaters on, from at least 10 hours to at least 15 continuous 
minutes, consistent with Technical Specification Task Force Traveler-
522, Revision 0, ``Revise Ventilation System Surveillance Requirements 
to Operate for 10 hours per Month,'' with minor variations.
    Date of issuance: November 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 199. A publicly-available version is in ADAMS under 
Accession No. ML15286A091; documents related to this amendment are 
listed in the Safety Evaluation (SE) enclosed with the amendment.
    Renewed Facility Operating License No. NPF-57: Amendment revised 
the Renewed Facility Operating License and TSs.
    Date of initial notice in Federal Register: January 20, 2015 (80 FR 
2751).
    The Commission's related evaluation of the amendment is contained 
in an SE dated November 30, 2015.
    No significant hazards consideration comments received: Yes. The 
comment received on Amendment No. 199 is addressed in the SE dated 
November 30, 2015.

Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296, 
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Limestone County, 
Alabama

    Date of amendment request: March 9, 2015, as supplemented by letter 
dated July 10, 2015.
    Brief description of amendments: The amendments adopted NRC-
approved Technical Specifications Task Force (TSTF) Standard Technical 
Specifications Change Traveler TSTF-535, ``Revise Shutdown Margin 
Definition to Address Advanced Fuel Designs'' (ADAMS Accession No. 
ML112200436), Revision 0, dated August 8, 2011, revising the Technical 
Specification (TS) definition of shutdown margin (SDM) to require 
calculation of SDM at the reactor moderator temperature corresponding 
to the most reactive state throughout the operating cycle (68 degrees 
Fahrenheit ([deg]F) or higher). The purpose is to address the boiling 
water reactor fuel designs, which may be more reactive at shutdown 
temperatures above 68[emsp14][deg]F.
    Date of issuance: December 4, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 291 (Unit 1), 316 (Unit 2), and 274 (Unit 3). A 
publicly-available version is in ADAMS under Accession No. ML15287A371, 
documents related to these amendments are listed in the Safety 
Evaluation (SE) enclosed with the amendments.
    Renewed Facility Operating License Nos. DPR-33, DPR-52, and DPR-68: 
Amendments revised the Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: June 23, 2015 (80 FR 
35985). The supplemental letter dated July 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 an SE dated December 4, 2015.
    No significant hazards consideration comments received: No.

Tennessee Valley Authority, Docket Nos. 50-327 and 50-328, Sequoyah 
Nuclear Plant, Units 1 and 2, Hamilton County, Tennessee

    Date of amendment request: December 2, 2014, as supplemented by 
letters dated September 11, 2015, and October 23, 2015.
    Brief description of amendments: The amendments revised Technical 
Specification (TS) 6.8.4.h (Improved Standard TS 5.5.14), ``Containment 
Leakage Rate Testing Program,'' by adopting Nuclear Energy Institute 
94-01, Revision 3-A, ``Industry Guideline for Implementing Performance-
Based Option of 10 CFR [title 10 of the Code of Federal Regulations] 
part 50, Appendix J,'' as the implementation document for the 
performance-based Option B of 10 CFR part 50, appendix J. The proposed 
changes would permanently extend the Type A containment integrated leak 
rate testing interval from 10 years to 15 years and the Type C local 
leakage rate testing intervals from 60 months to 75 months.
    Date of issuance: November 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 335 (Unit 1) and 328 (Unit 2). A publicly-available 
version is in ADAMS under Accession No. ML15320A218; documents related 
to these amendments are listed in the Safety Evaluation (SE) enclosed 
with the amendments.
    Renewed Facility Operating License Nos. DPR-77 and DPR-79: 
Amendments revised the Renewed Facility Operating Licenses and TSs.
    Date of initial notice in Federal Register: March 17, 2015 (80 FR 
13914). The supplemental letters dated September 11, 2015, 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 amendments is contained 
in an SE dated November 30, 2015.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 10th day of December 2015.

    For the Nuclear Regulatory Commission.
George A. Wilson, Jr.,
Deputy Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2015-31754 Filed 12-21-15; 8:45 am]
 BILLING CODE 7590-01-P