80 FR 48920 - Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 80, Issue 157 (August 14, 2015)

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 23, 2015, to August 5, 2015. The last biweekly notice was published on August 4, 2015.

[Federal Register Volume 80, Number 157 (Friday, August 14, 2015)]
[Notices]
[Pages 48920-48932]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2015-20138]



[[Page 48920]]

=======================================================================
-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[NRC-2015-0194]


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 23, 2015, to August 5, 2015. The last 
biweekly notice was published on August 4, 2015.

DATES: Comments must be filed by September 17, 2015. A request for a 
hearing must be filed by October 19, 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-2015-0194. 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: Sandra Figueroa, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 
20555-0001; telephone: 301-415-1262, email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Obtaining Information and Submitting Comments

A. Obtaining Information

    Please refer to Docket ID NRC-2015-0194 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-2015-0194.
     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-2015-0194, 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 48921]]

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 10 
days prior to the filing deadline, the participant should contact the 
Office of the Secretary by email at [email protected], or by 
telephone at 301-415-1677, to request (1) a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign documents and access the E-Submittal 
server for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a request or 
petition for hearing (even in instances in which the participant, or 
its counsel or representative, already holds an NRC-issued digital ID 
certificate). Based upon this information, the Secretary will establish 
an electronic docket for the hearing in this proceeding if the 
Secretary has not already established an electronic docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/getting-started.html. System requirements for accessing 
the E-Submittal server are detailed in the NRC's ``Guidance for 
Electronic Submission,'' which is available on the agency's public Web 
site at http://www.nrc.gov/site-help/e-submittals.html. Participants 
may attempt to use other software not listed on the Web site, but 
should note that the NRC's E-Filing system does not support unlisted 
software, and the NRC Meta System Help Desk will not be able to offer 
assistance in using unlisted software.
    If a participant is electronically submitting a document to the NRC 
in accordance with the E-Filing rule, the participant must file the 
document using the NRC's online, Web-based submission form. In order to 
serve documents through the Electronic Information Exchange System, 
users will be required to install a Web browser plug-in from the NRC's 
Web site. Further information on the Web-based submission form, 
including the installation of the Web browser plug-in, is available on 
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
    Once a participant has obtained a digital ID certificate and a 
docket has been created, the participant can then submit a request for 
hearing or petition for leave to intervene. Submissions

[[Page 48922]]

should be in Portable Document Format (PDF) in accordance with NRC 
guidance available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the 
time the documents are submitted through the NRC's E-Filing system. To 
be timely, an electronic filing must be submitted to the E-Filing 
system no later than 11:59 p.m. Eastern Time on the due date. Upon 
receipt of a transmission, the E-Filing system time-stamps the document 
and sends the submitter an email notice confirming receipt of the 
document. The E-Filing system also distributes an email notice that 
provides access to the document to the NRC's Office of the General 
Counsel and any others who have advised the Office of the Secretary 
that they wish to participate in the proceeding, so that the filer need 
not serve the documents on those participants separately. Therefore, 
applicants and other participants (or their counsel or representative) 
must apply for and receive a digital ID certificate before a hearing 
request/petition to intervene is filed so that they can obtain access 
to the document via the E-Filing system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System 
Help Desk through the ``Contact Us'' link located on the NRC's public 
Web site at http://www.nrc.gov/site-help/e-submittals.html, by email to 
[email protected], or by a toll-free call at 1-866-672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., 
Eastern Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland, 20852, Attention: Rulemaking and Adjudications Staff. 
Participants filing a document in this manner are responsible for 
serving the document on all other participants. Filing is considered 
complete by first-class mail as of the time of deposit in the mail, or 
by courier, express mail, or expedited delivery service upon depositing 
the document with the provider of the service. A presiding officer, 
having granted an exemption request from using E-Filing, may require a 
participant or party to use E-Filing if the presiding officer 
subsequently determines that the reason for granting the exemption from 
use of E-Filing no longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the 
Commission, or the presiding officer. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law requires submission of such information. 
However, in some instances, a request to intervene will require 
including information on local residence in order to demonstrate a 
proximity assertion of interest in the proceeding. With respect to 
copyrighted works, except for limited excerpts that serve the purpose 
of the adjudicatory filings and would constitute a Fair Use 
application, participants are requested not to include copyrighted 
materials in their submission.
    Petitions for leave to intervene must be filed no later than 60 
days from the date of publication of this notice. Requests for hearing, 
petitions for leave to intervene, and motions for leave to file new or 
amended contentions that are filed after the 60-day deadline will not 
be entertained absent a determination by the presiding officer that the 
filing demonstrates good cause by satisfying the three factors in 10 
CFR 2.309(c)(1)(i)-(iii).
    For further details with respect to these license amendment 
applications, see the application for amendment which is available for 
public inspection in ADAMS and at the NRC's PDR. For additional 
direction on accessing information related to this document, see the 
``Obtaining Information and Submitting Comments'' section of this 
document.
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287, 
Oconee Nuclear Station, Units 1, 2, and 3 (ONS), Oconee County, South 
Carolina
    Date of amendment request: June 23, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15183A060.
    Description of amendment request: The amendment would involve 
upgrading the ONS, Emergency Action Levels based on NEI 99-01, Revision 
6, ``Development of Emergency Action Levels for Non-Passive Reactors.'' 
Pursuant to 10 CFR part 50, appendix E, section IV.B, Duke Energy 
requested NRC approval of this proposed change to the ONS Emergency 
Plan prior to implementation.
    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 ONS Emergency Plan and do not alter the 
requirements of the Operating License or the Technical 
Specifications. The proposed changes do not modify plant equipment 
and do not impact failure modes that could lead to an accident. 
Additionally, the proposed changes do not impact the consequence of 
an analyzed accident since the changes do not affect 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 ONS Emergency Plan and do not alter the 
requirements of the Operating License or the Technical 
Specifications. They do not modify 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 malfunction 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 an accident 
previously evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    These changes affect the ONS Emergency Plan and do not alter the 
requirements of the Operating License or the Technical 
Specifications. The proposed changes do not affect the assumptions 
used in the accident analysis, nor do they affect the operability 
requirements for equipment important to plant safety.
    Therefore, the proposed changes will not result in a significant 
reduction in the margin

[[Page 48923]]

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 Tryon Street--DEC45A, Charlotte, NC 
28202-1802.
    NRC Branch Chief: Robert J. Pascarelli.
Duke Energy Progress, Inc., Docket Nos. 50-325 and 50-324; Brunswick 
Steam Electric Plant, Unit Nos. 1 and 2, Brunswick County, North 
Carolina; Docket No. 50-400; Shearon Harris Nuclear Power Plant, Unit 
1, Wake County, North Carolina; 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; and Docket Nos. 50-
269, 50-270, and 50-287, Oconee Nuclear Station, Units 1, 2, and 3, 
Oconee County, South Carolina
    Date of amendment request: June 24, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15175A438.
    Description of amendment request: The proposed change revises or 
adds Surveillance Requirements to verify that the system locations 
susceptible to gas accumulation are sufficiently filled with water and 
to provide allowances which permit performance of the verification. The 
changes are being made to address the concerns discussed in NRC Generic 
Letter 2008-01, ``Managing Gas Accumulation in Emergency Core Cooling, 
Decay Heat Removal, and Containment Spray Systems'' (ADAMS Accession 
No. ML072910759). The proposed amendment references TSTF-523, Revision 
2, ``Generic Letter 2008-01, Managing Gas Accumulation'' (79 FR 2700; 
January 15, 2014).
    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 revises or adds Surveillance Requirement(s) 
(SRs) that require verification that the Emergency Core Cooling 
System (ECCS), the Decay Heat Removal (DHR)/Residual Heat Removal 
(RHR) System, the Containment Spray/Reactor Building Spray System, 
and the Reactor Core Isolation Cooling (RCIC) System are not 
rendered inoperable due to accumulated gas and to provide allowances 
which permit performance of the revised verification. Gas 
accumulation in the subject systems 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 SRs ensure that the subject systems continue to be capable 
to perform their assumed safety function and are not rendered 
inoperable due to gas accumulation. Thus, the consequences of any 
accident previously evaluated are not significantly increased.
    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 revises or adds SRs that require 
verification that the ECCS, the DHR/RHR System, the Containment 
Spray/Reactor Building Spray System, and the RCIC System are not 
rendered inoperable due to accumulated gas and to provide allowances 
which permit performance of the revised verification. 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 a 
margin of safety?
    Response: No.
    The proposed change revises or adds SRs that require 
verification that the ECCS, the DHR/RHR System, the Containment 
Spray/Reactor Building Spray System, and the RCIC System are not 
rendered inoperable due to accumulated gas and to provide allowances 
which permit performance of the revised verification. The proposed 
change adds new requirements to manage gas accumulation in order to 
ensure the subject systems are capable of performing their assumed 
safety functions. The proposed SRs are more comprehensive than the 
current SRs and will ensure that the assumptions of the safety 
analysis are protected. 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: Lara S. Nichols, Deputy General Counsel, 
Duke Energy Corporation, 550 South Tryon Street--DEC45A, Charlotte, NC 
28202-1802.
    NRC Branch Chiefs: Robert J. Pascarelli and Shana Helton.
Luminant Generation Company LLC, Docket Nos. 50-445 and 50-446, 
Comanche Peak Nuclear Power Plant, Units 1 and 2 (CPNPP), Somervell 
County, Texas
    Date of amendment request: June 30, 2015. A publicly-available 
version is in ADAMS under Accession No. ML15191A175.
    Description of amendment request: The amendment involves upgrading 
selected CPNPP Emergency Action Levels (EALs) based on Nuclear Energy 
Institute (NEI) 99-01, Revision 6, ``Development of Emergency Action 
Levels for Non-Passive Reactors,'' dated November 2012 (ADAMS Accession 
No. ML12326A805), using the guidance of NRC Regulatory Issue Summary 
2003-18, Supplement 2, ``Use of NEI 99-01, Methodology for Development 
of EALs,'' dated December 12, 2005 (ADAMS Accession No. ML051450482).
    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 CPNPP 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.

[[Page 48924]]

    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 CPNPP 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 accident 
initiators 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 CPNPP 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: Timothy P. Matthews, Esq., Morgan, Lewis and 
Bockius, 1111 Pennsylvania Avenue NW., Washington, DC 20004.
    NRC Branch Chief: Michael T. Markley.
South Carolina Electric & Gas Company, South Carolina Public Service 
Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station, Unit 
No. 1, Fairfield County, South Carolina
    Date of amendment request: July 22, 2015. A publicly-available 
version is in ADAMS Accession No. ML15205A291.
    Description of amendment request: The licensee proposes to revise 
Technical Specification Section 6.0, ``Administrative Controls'' by 
changing the ``Shift Supervisor'' title to ``Shift Manager.''
    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 to the Technical Specifications (TS) 
regarding Shift Supervisor to Shift Manager are administrative 
changes. It has no impact on accident initiators or plant equipment 
and thus does not affect the probability or consequences of an 
accident.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed change does not involve a change to the physical 
plant or operations. This is an administrative title change that 
does not contribute to accident initiation. Therefore, it does not 
produce a new accident scenario or produce a new type of equipment 
malfunction.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    Since the change is administrative and changes no previously 
evaluated accidents or creates no possibility for any new 
unevaluated accidents to occur, there is no reduction in the margin 
of safety. This change also does not affect plant equipment or 
operation and therefore does not affect safety limits or limiting 
safety systems settings.

    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: J. Hagood Hamilton, Jr., South Carolina 
Electric & Gas Company, Post Office Box 764, Columbia, South Carolina 
29218.
    NRC Branch Chief: Robert J. Pascarelli.
STP Nuclear Operating Company, Docket Nos. 50-498 and 50-499, South 
Texas Project (STP), Units 1 and 2, Matagorda County, Texas
    Date of amendment request: April 29, 2015, as supplemented by 
letter dated June 29, 2015. Publicly-available versions are in ADAMS 
under Accession Nos. ML15128A352 and ML15198A147, respectively.
    Description of amendment request: The amendment would revise the 
Integrated Leak Rate Test performance interval from 10 years to 15 
years in Technical Specification (TS) 3.8.3.j, ``Containment Leakage 
Rate Testing Program,'' in accordance with Nuclear Energy Institute 94-
01, Revision 2A, ``Industry Guideline for Implementing Performance-
Based Option of 10 CFR part 50, appendix J,'' dated October 2008 (ADAMS 
Accession No. ML100620847).
    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 to the TS involves the extension of the 
STP, Units 1 and 2 Type A containment test interval to 15 years. The 
current Type A test interval of 120 months (10 years) would be 
extended on a permanent basis to no longer than 15 years from the 
last Type A test. Extensions of up to nine months (total maximum 
interval of 189 months for Type A tests) are permissible only for 
non-routine emergent conditions. The proposed extension does not 
involve either a physical change to the plant or a change in the 
manner in which the plant is operated or controlled. The containment 
is designed to provide an essentially leak tight barrier against the 
uncontrolled release of radioactivity to the environment for 
postulated accidents. As such, the containment and the testing 
requirements invoked to periodically demonstrate the integrity of 
the containment exist to ensure the plant's ability to mitigate the 
consequences of an accident, and do not involve the prevention or 
identification of any precursors of an accident. The change in dose 
risk for changing the Type A test frequency from once-per-ten years 
to once-per-fifteen-years, measured as an increase to the total 
integrated dose risk for all internal events accident sequences for 
STP, of 0.123 person [roentgen equivalent man per year (rem/yr)] for 
Unit 1 and Unit 2 using the [Electric Power Research Institute 
(EPRI)] guidance with the base case corrosion included. Therefore, 
this proposed extension does not involve a significant increase in 
the probability of an accident previously evaluated.
    As documented in NUREG-1493, [``Performance-Based Containment 
Leak-Test Program,'' dated January 1995] Type B and C tests have 
identified a very large percentage of containment leakage paths, and 
the percentage of containment leakage paths that are detected only 
by Type A testing is very small. The STP, Units 1 and 2 Type A test 
history supports this conclusion.
    The integrity of the containment is subject to two types of 
failure mechanisms that can be categorized as: (1) Activity based, 
and; (2) time based. Activity based failure mechanisms are defined 
as degradation due to system and/or component modifications or 
maintenance. Local leak rate test requirements and administrative 
controls such as configuration management and

[[Page 48925]]

procedural requirements for system restoration ensure that 
containment integrity is not degraded by plant modifications or 
maintenance activities. The design and construction requirements of 
the containment combined with the containment inspections performed 
in accordance with ASME Section XI, the Maintenance Rule, and TS 
requirements serve to provide a high degree of assurance that the 
containment would not degrade in a manner that is detectable only by 
a Type A test. Based on the above, the proposed extensions do not 
significantly increase the consequences of an accident previously 
evaluated.
    The proposed amendment also deletes exceptions previously 
granted to allow one-time extensions of the ILRT test frequency for 
both Units 1 and 2. These exceptions were for activities that have 
already taken place so their deletion is solely an administrative 
action that has no effect on any component and no impact on how the 
units are operated.
    Therefore, the proposed change does not result in 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 amendment to the TS involves the extension of the 
STP, Unit 1 and 2 Type A containment test interval to 15 years. The 
containment and the testing requirements to periodically demonstrate 
the integrity of the containment exist to ensure the plant's ability 
to mitigate the consequences of an accident do not involve any 
accident precursors or initiators. The proposed change does not 
involve a physical change to the plant (i.e., no new or different 
type of equipment will be installed) or a change to the manner in 
which the plant is operated or controlled.
    The proposed amendment also deletes exceptions previously 
granted to allow one-time extensions of the ILRT test frequency for 
both Units 1 and 2. These exceptions were for activities that would 
have already taken place by the time this amendment is approved; 
therefore, their deletion is solely an administrative action that 
does not result in any change in how the units are operated.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any previously 
evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed amendment to TS 6.8.3.j involves the extension of 
the STP, Units 1 and 2 Type A containment test interval to 15 years. 
This amendment does not alter the manner in which safety limits, 
limiting safety system set points, or limiting conditions for 
operation are determined. The specific requirements and conditions 
of the TS Containment Leak Rate Testing Program exist to ensure that 
the degree of containment structural integrity and leak-tightness 
that is considered in the plant safety analysis is maintained. The 
overall containment leak rate limit specified by TS is maintained.
    The proposed change involves only the extension of the interval 
between Type A containment leak rate tests for STP, Units 1 and 2. 
The proposed surveillance interval extension is bounded by the 15-
year ILRT Interval currently authorized within NEI 94-01, Revision 
2-A. Industry experience supports the conclusion that Type B and C 
testing detects a large percentage of containment leakage paths and 
that the percentage of containment leakage paths that are detected 
only by Type A testing is small. The containment inspections 
performed in accordance with [American Society for Mechanical 
Engineers (ASME) Boiler and Pressure Vessel Code,] Section Xl, TS 
and the Maintenance Rule serve to provide a high degree of assurance 
that the containment would not degrade in a manner that is 
detectable only by Type A testing. The combination of these factors 
ensures that the margin of safety in the plant safety analysis is 
maintained. The design, operation, testing methods and acceptance 
criteria for Type A, B, and C containment leakage tests specified in 
applicable codes and standards would continue to be met, with the 
acceptance of this proposed change, since these are not affected by 
changes to the Type A and Type C test intervals.
    The proposed amendment also deletes exceptions previously 
granted to allow one-time extensions of the ILRT test frequency for 
both Units 1 and 2. These exceptions were for activities that would 
have already taken place by the time this amendment is approved; 
therefore, their deletion is solely an administrative action and 
does not change how the units are operated and maintained. Thus, 
there is no reduction in any 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 standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
request for amendments involves no significant hazards consideration.
    NRC Branch Chief: Michael T. Markley.

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.
Susquehanna Nuclear, LLC, Docket Nos. 50-387 and 50-388, Susquehanna 
Steam Electric Station (SSES), Units 1 and 2, Luzerne County, 
Pennsylvania
    Date of amendment request: August 11, 2014, as supplemented by 
letters dated April 6, 2015, and July 16, 2015. Publicly-available 
versions are in ADAMS under Accession Nos. ML14223A780, ML15097A386, 
and ML15197A256, respectively.
    Brief description of amendment request: The amendment proposes 
changes to SSES, Units 1 and 2, Technical Specification 3.4.10, ``RCS 
[Reactor Coolant System] Pressure and Temperature (P/T) Limits,'' which 
includes revisions to the P/T Limits curves.
    Date of publication of individual notice in Federal Register: July 
30, 2015 (80 FR 45559).
    Expiration date of individual notice: August 31, 2015 (public 
comments); September 28, 2015 (hearing requests).

IV. Notice of Issuance of Amendments to Facility Operating Licenses and 
Combined Licenses

    During the period since publication of the last biweekly notice, 
the Commission has issued the following amendments. The Commission has 
determined for each of these amendments that the application complies 
with the standards and requirements of the Atomic Energy Act 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

[[Page 48926]]

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. 50-336, Millstone Power 
Station, Unit No. 2 (MPS2), New London County, Connecticut
    Date of amendment request: June 30, 2014, as supplemented by letter 
dated January 29, 2015.
    Brief description of amendment: The amendment revised the Technical 
Specifications (TSs) by adopting approved Technical Specification Task 
Force (TSTF) traveler TSTF-426, Revision 5, ``Revise or Add Actions to 
Preclude Entry into LCO 3.0.3--RITSTF Initiatives 6b and 6c,'' and 
providing a short completion time to restore an inoperable system for 
conditions under which the previous TS required a plant shutdown. The 
amendment also reformats each proposed MPS2 custom TS ACTION format to 
a two-column tabular format.
    Date of issuance: July 29, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days from the date of issuance.
    Amendment No.: 321. A publicly-available version is in ADAMS under 
Accession No. ML15187A326; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-65: Amendment revised 
the Renewed Operating License and TSs.
    Date of initial notice in Federal Register: December 23, 2014 (79 
FR 77044). The supplemental letter dated January 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 29, 2015.
    No significant hazards consideration comments received: No.
Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power 
Station, Unit No. 3, New London County, Connecticut
    Date of amendment request: November 6, 2013, as supplemented on 
November 14, 2014, and February 9, 2015.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 3/4.5.4, ``Refueling Water Storage Tank,'' and TS 3/
4.6.2.1, ``Depressurization and Cooling Systems, Containment Quench 
Spray System,'' to provide additional operational margin for control of 
the Refueling Water Storage Tank. The amendment also made a clarifying 
editorial change to the TS 3/4.5.4 action statement.
    Date of issuance: July 27, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 12 days from the date of issuance.
    Amendment No.: 262. A publicly-available version is in ADAMS under 
Accession No. ML15187A011; 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 Operating License and TSs.
    Date of initial notice in Federal Register: November 25, 2014 (79 
FR 70212). The supplemental letters dated November 14, 2014, and 
February 9, 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 27, 2015.
    No significant hazards consideration comments received: No.
Dominion Nuclear Connecticut, Inc., Docket No. 50-423, Millstone Power 
Station, Unit, No. 3, New London County, Connecticut
    Date of amendment request: August 19, 2014, as supplemented on 
January 26, 2015.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 3/4.7.1.2, ``Auxiliary Feedwater System,'' 
Surveillance Requirement 4.7.1.2.1.b. by replacing the surveillance 
frequency and acceptance criteria for the Auxiliary Feedwater (AFW) 
pumps with a reference to the Inservice Testing Program (TS 4.0.5) for 
the specific pump testing acceptance criteria and the surveillance 
frequency. The amendment also added information on suitable plant 
conditions for performance of the steam turbine driven AFW pump 
surveillance.
    Date of issuance: July 28, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days from the date of issuance.
    Amendment No.: 263. A publicly-available version is in ADAMS under 
Accession No. ML15187A186; 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 Operating License and TSs.
    Date of initial notice in Federal Register: May 26, 2015 (80 FR 
30099).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated July 28, 2015.
    No significant hazards consideration comments received: No.
Duke Energy Progress, Inc., Docket Nos. 50-325, 50-324, 50-400, 
Brunswick Steam Electric Plant, Units 1 and 2 (Brunswick), and Shearon 
Harris Nuclear Power Plant, Unit 1 (Harris), Brunswick, Wake, and 
Chatham Counties, North Carolina
    Date of amendment request: December 22, 2014, as supplemented by 
letters dated March 4, 2015; June 1, 2015; June 10, 2015; June 24, 
2015; and July 29, 2015.
    Brief description of amendments: By orders dated July 6, 2015, as 
published in the Federal Register on July 14, 2015 (80 FR 41095 and 80 
FR 41097), the NRC approved direct license transfers for Brunswick and 
Harris. These amendments reflect the direct transfer of the licenses of 
the percent of ownership from North Carolina Eastern Municipal Power 
Agency to Duke Energy Progress, Inc., keeping Duke Energy as the sole 
owner and licensee.
    Date of issuance: July 31, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment Nos.: 267 for Brunswick, Unit 1, 295 for Unit 2, and 147 
for Harris, Unit 1. Publicly-available versions of the Brunswick and 
Harris amendments are in ADAMS under Accession No. ML15161A121, and the 
orders are in ADAMS under Accession Nos. ML15159A602 and ML15159A617, 
respectively. Documents related to these amendments are listed in the 
safety evaluation (SE) enclosed with the order dated July 6, 2015. 
Subsequent to the issuance of the orders, the licensee submitted a 
letter dated July 29, 2015

[[Page 48927]]

(ADAMS Accession No. ML15210A049). The letter provided additional 
notifications of regulatory approvals and the closing transaction date, 
as required by the order.
    Renewed Facility Operating License Nos. DPR-71, DPR-62, and NPF-63: 
The amendments revised the Renewed Facility Operating Licenses.
    Date of initial notices in Federal Register: April 21, 2015 (80 FR 
22224 and 22228). The supplemental letters dated June 1, 2015; June 10, 
2015; June 24, 2015; and July 29, 2015, provided additional information 
that clarified the application, did not expand the scope of the 
application as originally noticed, and did not change the staff's 
original proposed no significant hazards consideration determination as 
published in the Federal Register.
    The Commission's related evaluation of the amendments is contained 
in an SE dated July 6, 2015 (ADAMS No. ML15159A632).
    No significant hazards consideration comments received: No.
Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287, 
Oconee Nuclear Station, Units 1, 2, and 3, Oconee County, South 
Carolina
    Date of amendment request: September 18, 2014.
    Brief description of amendments: The amendments revise the 
Technical Specifications to define a new time limit for restoring 
inoperable Reactor Coolant System (RCS) leakage detection 
instrumentation to operable status and establish alternate methods of 
monitoring RCS leakage when one or more required monitors are 
inoperable in accordance with Technical Specifications Task Force 
Traveler 513, Revision 3, ``Revise Pressurized-Water Reactor 
Operability Requirements and Actions for Reactor Coolant System Leakage 
Instrumentation.''
    Date of issuance: July 27, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days.
    Amendment Nos.: 394 for Unit 1, 396 for Unit 2, and 395 for Unit 3. 
A publicly-available version is in ADAMS under Accession No. 
ML15170A055; documents related to these amendments are listed in the 
Safety Evaluation enclosed with the amendments.
    Facility Operating License Nos. DPR-38, DPR-47, and DPR-55: The 
amendments revised the Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: May 26, 2015 (80 FR 
30100).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated July 27, 2015.
    No significant hazards consideration comments received: No.
Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc., 
Docket No. 50-458, River Bend Station, Unit 1 (RBS), West Feliciana 
Parish, Louisiana
    Date of amendment request: July 9, 2014, as supplemented by letters 
dated February 24, June 3, and July 16, 2015.
    Brief description of amendment: The amendment revised the RBS 
Technical Specifications (TSs) Surveillance Requirements (SRs) related 
to the steady state voltage, frequency and test load limits for the 
emergency diesel generators Diesel Generator (DG) 1A, DG 1B and DG 1C. 
Specifically, the amendment revised the SR Acceptance Criteria 
Tolerance Band (ACTB) for TS SRs 3.8.1.2, 3.8.1.3, 3.8.1.7, 3.8.1.10, 
3.8.1.11, 3.8.1.12, 3.8.1.14, 3.8.1.15, 3.8.1.19 and 3.8.1.20. The 
changes will lower the upper bound of the frequency SR ACTB, lower the 
upper bound of the voltage SR ACTB for DG 1A and DG 1B (existing DG 1C 
voltage SR ACTB is retained), and raise the lower bound of the test 
load SR ACTB.
    Date of issuance: July 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
60 days from the date of issuance.
    Amendment No.: 187. A publicly-available version is in ADAMS under 
Accession No. ML15187A127; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. NPF-47: The amendment revised the 
Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: November 12, 2014 (79 
FR 67201). The supplements dated February 24, June 3, and July 16, 
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 30, 2015.
    No significant hazards consideration comments received: No.
Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric 
Station, Unit 3, St. Charles Parish, Louisiana
    Date of amendment request: October 1, 2014, as supplemented by 
letter dated February 2, 2015.
    Brief description of amendment: The amendment relocated Technical 
Specification (TS) 3/4.9.6, ``Refueling Machine,'' and TS 3/4.9.7, 
``Crane Travel--Fuel Handling Building,'' to the Technical Requirements 
Manual.
    Date of issuance: July 29, 2015.
    Effective date: As of the date of issuance and shall be implemented 
60 days from the date of issuance.
    Amendment No.: 243. A publicly-available version is in ADAMS under 
Accession No. ML15174A227; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Operating License No. NPF-38: The amendment revised the 
Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: March 3, 2015 (80 FR 
11475). The supplemental letter dated February 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 NRC staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated July 29, 2015.
    No significant hazards consideration comments received: No.

[[Page 48928]]

Exelon Generation Company, LLC, Docket Nos. STN 50-456, STN 50-457 and 
72-73, Braidwood Station, Units 1 and 2, Will County, Illinois
Exelon Generation Company, LLC, Docket Nos. STN 50-454, STN 50-455 and 
72-68, Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois
Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power 
Station, Unit No. 1, DeWitt County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-10, 50-237, 50-249 and 
72-37, Dresden Nuclear Power Station, Units 1, 2 and 3, Grundy County, 
Illinois
Exelon Generation Company, LLC, Docket Nos. 50-373, 50-374 and 72-70, 
LaSalle County Station, Units 1 and 2, LaSalle County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-352, 50-353 and 72-65, 
Limerick Generating Station, Unit 1 and 2, Montgomery County, 
Pennsylvania
Exelon Generation Company, LLC, et al., Docket No. 50-219 and 72-15, 
Oyster Creek Nuclear Generating Station, Ocean County, New Jersey
Exelon Generation Company, LLC, and PSEG Nuclear LLC, Docket Nos. 50-
171, 50-277, 50-278 and 72-29, Peach Bottom Atomic Power Station, Units 
1, 2 and 3, York and Lancaster Counties, Pennsylvania
Exelon Generation Company, LLC, Docket Nos. 50-254, 50-265 and 70-53, 
Quad Cities Nuclear Power Station, Units 1 and 2, Rock Island County, 
Illinois
Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island 
Nuclear Station, Unit 1, Dauphin County, Pennsylvania
Exelon Generation Company, LLC, Docket No. 50-320, Three Mile Island 
Nuclear Station, Unit 2, Dauphin County, Pennsylvania
    Date of amendment request: May 30, 2014, as supplemented by letters 
dated March 2 and June 5, 2015.
    Brief description of amendments: The amendments revised the 
Emergency Plans for the affected facilities to adopt the Nuclear Energy 
Institute's (NEl's) revised Emergency Action Level (EAL) schemes 
described in NEI 99-01, Revision 6, ``Development of Emergency Action 
Levels for Non-Passive Reactors.''
    Date of issuance: July 28, 2015.
    Effective date: As of the date of issuance and shall be implemented 
on or before April 29, 2016.
    Amendment Nos.: 184, 184, 190, 190, 205, 45, 245, 238, 215, 201, 
217, 179, 287, 13, 300, 303, 258, 253, and 287. A publicly-available 
version is in ADAMS under Accession No. ML15141A058; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Facility Operating License Nos. NPF-72, NPF-77, NPF-37, NPF-66, 
NPF-62, DPR-2, DPR-19, DPR-25, NPF-11, NPF-18, NPF-39, NPF-85, DPR-16, 
DPR-12, DPR-44, DPR-56, DPR-29, DPR-30, and DPR-50: The amendments 
revised the Emergency Plans.
    Date of initial notice in Federal Register: September 16, 2014 (79 
FR 55511). The supplemental letters dated March 2 and June 5, 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 28, 2015.
    No significant hazards consideration comments received: No from 
Pennsylvania and New Jersey, and Yes from the state of Illinois. The 
Safety Evaluation dated July 28, 2015, provides the discussion of the 
comments received from the State of Illinois.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-457, 
Braidwood Station, Units 1 and 2, Will County, Illinois
Exelon Generation Company, LLC, Docket Nos. STN 50-454 and STN 50-455, 
Byron Station, Unit Nos. 1 and 2, Ogle County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert 
Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland
Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power 
Station, Unit No. 1, DeWitt County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden 
Nuclear Power Station, Units 2 and 3, Grundy County, Illinois
Exelon Generation Company, LLC, Docket Nos. 50-373 and 50-374, LaSalle 
County Station, Units 1 and 2, LaSalle County, Illinois
Exelon Generation Company, LLC, Docket No. 50-352 and No. 50-353, 
Limerick Generating Station, Unit 1 and 2, Montgomery County, 
Pennsylvania
Exelon Generation Company, LLC, Docket Nos. 50-220 and 50-410, Nine 
Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York
Exelon Generation Company, LLC, et al., Docket No. 50-219, Oyster Creek 
Nuclear Generating Station, Ocean County, New Jersey
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
Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad 
Cities Nuclear Power Station, Units 1 and 2, Rock Island County, 
Illinois
Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear 
Power Plant, Wayne County, New York
Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island 
Nuclear Station, Unit 1, Dauphin County, Pennsylvania
    Date of amendment request: August 29, 2014.
    Brief description of amendments: The amendments approved the 
extension of the completion date for Milestone 8 of the Cyber Security 
Plan implementation schedules.
    Date of issuance: July 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.

[[Page 48929]]

    Amendment Nos.: 185, 185, 191, 191, 312, 290, 206, 246, 239, 216, 
202, 218, 180, 219, 149, 288, 301, 304, 259, 254, 117, and 288. A 
publicly-available version is in ADAMS under Accession No. ML15153A282; 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Facility Operating License Nos. NPF-72, NPF-77, NPF-37, NPF-66, 
DPR-53, DPR-69, NPF- 62, DPR-19, DPR-25, NPF-11, NPF-18, NPF-39, NPF-
85, DPR-63, NPF-69, DPR-16, DPR-44, DPR-56, DPR-29, DPR-30, DPR-18, 
DPR-50: The amendments revised the Licenses.
    Date of initial notice in Federal Register: May 5, 2015 (80 FR 
25719).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated July 30, 2015.
    No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket Nos. 50-317 and 50-318, Calvert 
Cliffs Nuclear Power Plant, Unit Nos. 1 and 2, Calvert County, Maryland
    Date of amendment request: January 13, 2014, as supplemented by 
letters dated November 3, 2014, March 3, 2015, and March 27, 2015.
    Brief description of amendments: These amendments revise the 
Technical Specifications (TSs) to add a new TS 3.7.18, ``Atmospheric 
Dump Valves (ADVs).'' The addition of these TSs addresses a degraded or 
non-conforming condition that was caused by not having TSs for the 
ADVs.
    Date of issuance: July 23, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: 311 and 289. A publicly-available version is in 
ADAMS under Accession No. ML15133A144; 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 License and TSs.
    Date of initial notice in Federal Register: July 22, 2014 (79 FR 
42548). The supplemental letters dated November 3, 2014, March 3, 2015, 
and March 27, 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 23, 2015.
    No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-317, Calvert Cliffs 
Nuclear Power Plant, Unit No. 1 (CCNPP1), Calvert County, Maryland
Exelon Generation Company, LLC, Docket No. 50-318, Calvert Cliffs 
Nuclear Power Plant, Unit No. 2 (CCNPP2), Calvert County, Maryland
Exelon Generation Company, LLC, Docket No. 50-244, R.E. Ginna Nuclear 
Power Plant (Ginna), Wayne County, New York
Exelon Generation Company, LLC, Docket No. 50-410, Nine Mile Point 
Nuclear Station, Unit No. 2 (NMP2), Oswego County, New York
    Date of amendment request: July 10, 2014, as supplemented by letter 
dated April 30, 2015.
    Brief description of amendment: The amendments revised and added 
several Technical Specification (TS) surveillance requirements to 
address concerns discussed in Generic Letter (GL) 2008-01, ``Managing 
Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and 
Containment Spray Systems.'' These changes are consistent with TS Task 
Force Traveler (TSTF) 523, Revision 2, GL 2008-01, Managing Gas 
Accumulation.
    Date of issuance: July 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days of issuance.
    Amendment No.: CCNPP1-313; CCNPP2-291; Ginna-118; NMP2-150. A 
publicly-available version of the amendments are in ADAMS under 
Accession No. ML15161A380; documents related to these amendments are 
listed in the Safety Evaluation enclosed with the amendments.
    Facility Operating License Nos. DPR-53 (CCNPP1), DPR-69 (CCNPP2), 
DPR-18 (Ginna), and NPF-69 (NMP2): The amendments revised the Facility 
Operating License and Technical Specifications.
    Date of initial notice in Federal Register: May 12, 2015, (80 FR 
27197). The supplemental letter dated April 30, 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 30, 2015.
    No significant hazards consideration comments received: No.
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: September 3, 2014, as supplemented by 
letter dated February 9, 2015.
    Brief description of amendments: The amendments revised the 
Technical Specifications to eliminate the main steam line (MSL) 
radiation monitor from initiating: (1) A reactor protection system 
automatic reactor scram; and (2) a primary containment isolation system 
isolation, including automatic closure of the MSL isolation valves, MSL 
drain valves, MSL sample line valves, residual heat removal system 
sample line valves, and reactor recirculation loop sample line valves.
    Date of issuance: July 28, 2015.
    Effective date: As of the date of issuance, to be implemented prior 
to startup from the fall 2016 refueling outage for Unit 2, and prior to 
startup from the fall 2015 refueling outage for Unit 3.
    Amendments Nos.: 299 and 302. A publicly-available version is in 
ADAMS under Accession No. ML15167A456; 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: November 12, 2014 (79 
FR 67201). The supplemental letter dated February 9, 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 28, 2015.
    No significant hazards consideration comments received: No.
Exelon Generation Company, LLC, Docket No. 50-289, Three Mile Island 
Nuclear Station, Unit No. 1, (TMI-1) Dauphin County, Pennsylvania
    Date of application for amendments: October 30, 2014, as 
supplemented by letter dated June 10, 2015.

[[Page 48930]]

    Brief description of amendment: The amendment revised the TMI-1 
Technical Specification Table 3.1.6.1, ``Pressure Isolation Check 
Valves Between the Primary Coolant System & LPIS [Low Pressure 
Injection System],'' maximum allowable leakage limits.
    Date of issuance: July 28, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days.
    Amendment Nos.: 286. A publicly-available version is in ADAMS under 
Accession No. ML15090A584; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. DPR-50: The amendment 
revised the Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: December 9, 2014 (79 FR 
73110). The supplemental letter dated June 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 amendment is contained 
in a Safety Evaluation dated July 28, 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 application for amendments: July 8, 2014, as supplemented 
by letter dated July 15, 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 27, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days of issuance.
    Amendment Nos.: 264 and 259. The amendments are in ADAMS under 
Accession No. ML15181A179; 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 TSs.
    Date of initial notice in Federal Register: October 14, 2014 (79 FR 
61661). The licensee's supplemental letter dated July 15, 2015, 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 27, 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 Creeks, Manitowoc 
County, Wisconsin
    Date of amendment request: July 3, 2014, as supplemented by letters 
dated December 8, 2014; March 19, 2015; and May 28, 2015.
    Brief description of amendments: The amendments revised the 
Technical Specifications (TSs) for Units 1 and 2 to relocate 
surveillance frequencies to licensee control as per Technical 
Specifications Task Force Traveler-425, Revision 3.
    Date of issuance: July 28, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment Nos.: 253 and 257. Publicly-available versions are in 
ADAMS under Accession No. ML15195A201; 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 Licenses and TSs.
    Date of initial notice in Federal Register: November 12, 2014 (79 
FR 67203). The supplemental letters dated December 8, 2014; March 19, 
2015; and May 28, 2015, provided additional information that clarified 
the application, did not expand the scope of the application as 
originally noticed, and did not change the staff's original proposed no 
significant hazards consideration determination as published in the 
Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated July 28, 2015.
    No significant hazards consideration comments received: No.
PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear 
Generating Station (Salem), Unit Nos. 1 and 2, Salem County, New Jersey
    Date amendment request: July 28, 2014, as supplemented by letter 
dated January 15, 2015.
    Brief description of amendments: The amendments revised the 
technical specification (TS) requirements regarding steam generator 
tube inspections and reporting as described in Technical Specifications 
Task Force (TSTF) Change Traveler TSTF-510, Revision 2, ``Revision to 
Steam Generator Program Inspection Frequencies and Tube Sample 
Selection.'' In addition, the amendments revise the Salem, Unit No. 2 
TSs 6.8.4.i, ``Steam Generator (SG) Program,'' and TS 6.9.1.10, ``Steam 
Generator Tube Inspection Report,'' to remove unnecessary information 
related to the original Salem, Unit No. 2 Westinghouse steam 
generators.
    Date of issuance: July 30, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment Nos.: 309 and 291. A publicly-available version is in 
ADAMS under Accession No. ML15153A230; documents related to these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Renewed Facility Operating License Nos. DPR-70 and DPR-75: The 
amendments revised the facility operating license and TSs.
    Date of initial notice in Federal Register: October 28, 2014 (79 FR 
64227). The supplemental letter dated January 15, 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 30, 2015.
    No significant hazards consideration comments received: No.
South Carolina Electric & Gas Company, Docket Nos. 52-027 and 52-028, 
Virgil C. Summer Nuclear Station, Units 2 and 3, Fairfield County, 
South Carolina
    Date of amendment request: September 11, 2014, and supplemented

[[Page 48931]]

by letters dated October 15, 2014 and December 18, 2014.
    Description of amendment: The amendment revises the Updated Final 
Safety Analysis Report by clarifying human diversity during the 
lifecycle development design process for the Component Interface Module 
and Diverse Actuation System.
    Date of issuance: July 17, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days of issuance.
    Amendment No.: 28. A publicly-available version is in ADAMS under 
Accession No. ML15176A703; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Combined Licenses No. NPF-93 and NPF-94: Amendment revised 
the Facility Combined Licenses.
    Date of initial notice in Federal Register: December 9, 2014 (79 FR 
73111). The supplemental letters dated October 15, 2014 and December 
18, 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 the Safety Evaluation dated July 17, 2015.
    No significant hazards consideration comments received: No.
South Carolina Electric and Gas Company, Docket Nos. 52-027 and 52-028, 
Virgil C. Summer Nuclear Station, Units 2 and 3 (VCSNS), Fairfield 
County, South Carolina
    Date of amendment request: January 27, 2015.
    Brief description of amendment: The amendments are to Combined 
License Nos. NPF-93 and NPF-94 for VCSNS Units 2 and 3. The amendments 
revise the VCSNS Units 2 and 3 Updated Final Safety Analysis Report 
(UFSAR) to clarify a human factors engineering operational sequence 
analysis related to the AP1000 Automatic Depressurization System and 
delete document WCAP-15847, ``AP1000 Quality Assurance Procedures 
Supporting NRC Review of AP1000 DCD Sections 18.2 and 18.8,'' that is 
incorporated by reference into the UFSAR. Both of the amendments 
constitute changes to information identified as Tier 2* information as 
defined in 10 CFR part 52, appendix D, section II.F.
    Date of issuance: June 2, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days of issuance.
    Amendment No.: 26. A publicly-available version is in ADAMS under 
Accession No. ML15131A445; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Facility Combined Licenses No. NPF-93 and NPF-94: Amendment revised 
the Facility Combined Licenses.
    Date of initial notice in Federal Register: March 17, 2015 (80 FR 
13912).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated June 2, 2015.
    No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50-
364, Joseph M. Farley Nuclear Plant (Farley), Units 1 and 2, Houston 
County, Alabama
Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 50-
425, Vogtle Electric Generating Plant (VEGP), Units 1 and 2, Burke 
County, Georgia
Southern Nuclear Operating Company, Inc., Georgia Power Company, 
Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, 
City of Dalton, Georgia, Docket Nos. 50-321 and 50-366, Edwin I. Hatch 
Nuclear Plant, Unit Nos. 1 and 2, Appling County, Georgia
    Date of application for amendment: December 30, 2014.
    Brief description of amendments: The amendments revise the date of 
the full implementation of the Cyber Security Plans.
    Date of issuance: August 3, 2015.
    Effective date: As of its date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment Nos.: Farley Unit 1-199, Farley Unit 2-195, VEGP Unit 1-
175, VEGP Unit 2-157, Hatch Unit 1-274, and Hatch Unit 2-219. A 
publicly-available version is in ADAMS under Accession No. ML15180A334, 
documents related to these amendments are listed in the Safety 
Evaluation enclosed with the amendments.
    Facility Operating License Nos. NPF-2, NPF-8, NPF-68, NPF-81, DPR-
57, NPF-5: The amendments revised the Renewed Facility Operating 
Licenses.
    Date of initial notice in Federal Register: March 3, 2015 (80 FR 
11492).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated August 3, 2015.
    No significant hazards consideration comments received: No.
Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, 
North Anna Power Station, Units 1 and 2, Louisa County, Virginia
    Date of application for amendment: August 27, 2014, as supplemented 
by letter dated February 16, 2015.
    Brief description of amendment: The license amendments approved the 
changes to the Technical Specification (TS) 3.4.3, ``[Reactor Coolant 
System] RCS Pressure and Temperature (P-T) Limits'' to address vacuum 
fill operations of the RCS to meet the requirements of 10 CFR part 50, 
appendix G. Specifically, this will revise TS figures 3.4.3-1 and 
3.4.3-2, RCS Heatup and Cooldown Limitations respectively.
    Date of issuance: July 27, 2015.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos.: 275 and 257. A publicly-available version is in 
ADAMS under Accession No. ML15187A424; documents related to these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Renewed Facility Operating License Nos. NPF-4 and NPF-7: Amendments 
revised the Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: October 14, 2014, (79 
FR 61663). The supplemental letter dated February 16, 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.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated July 27, 2015.
    No significant hazards consideration comments received: No.
Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek 
Generating Station, Coffey County, Kansas
    Date of amendment request: November 20, 2014, as supplemented by 
letters dated March 18 and May 4, 2015.
    Brief description of amendment: The amendment revised the Technical 
Specification (TS) requirements to address NRC Generic Letter 2008-01, 
``Managing Gas Accumulation in Emergency Core Cooling, Decay Heat 
Removal, and Containment Spray Systems,'' as described in Technical 
Specification Task Force (TSTF) Traveler TSTF-523, Revision 2, 
``Generic Letter 2008-01, Managing Gas Accumulation.''

[[Page 48932]]

    Date of issuance: July 28, 2015.
    Effective date: As of its date of issuance and shall be implemented 
within 90 days of the date of issuance.
    Amendment No.: 212. A publicly-available version is in ADAMS under 
Accession No. ML15169A213; documents related to this amendment are 
listed in the Safety Evaluation enclosed with the amendment.
    Renewed Facility Operating License No. NPF-42. The amendment 
revised the Operating License and Technical Specifications.
    Date of initial notice in Federal Register: March 31, 2015 (80 FR 
17105). The supplemental letters dated March 18 and May 4, 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 28, 2015.
    No significant hazards consideration comments received: No.

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

    For the Nuclear Regulatory Commission.
A. Louise Lund,
Acting Director, Division of Operating Reactor Licensing, Office of 
Nuclear Reactor Regulation.
[FR Doc. 2015-20138 Filed 8-13-15; 8:45 am]
BILLING CODE 7590-01-P