[Federal Register Volume 79, Number 109 (Friday, June 6, 2014)]
[Notices]
[Pages 32767-32773]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2014-13217]


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NUCLEAR REGULATORY COMMISSION

[NRC-2014-0132]


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 May 15 to May 28, 2014. The last biweekly 
notice was published on May 27, 2014.

DATES: Comments must be filed by July 7, 2014. A request for a hearing 
must be filed by August 5, 2014.

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-2014-0132. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422;

[[Page 32768]]

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: 3WFN-06-A44M, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001.
    For additional direction on accessing information and submitting 
comments, see ``Accessing Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

FOR FURTHER INFORMATION CONTACT: Janet Burkhardt, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington DC 
20555-0001; telephone: 301-415-1384, email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Accessing Information and Submitting Comments

A. Accessing Information

    Please refer to Docket ID NRC-2014-0132 when contacting the NRC 
about the availability of information regarding this document. You may 
access publicly-available information related to this action by the 
following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2014-0132.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access 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-2014-0132 in the subject line of your 
comment submission, in order to ensure that the NRC is able to make 
your comment submission available to the public in this docket.
    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 Sec.  50.92 of Title 10 of the Code of 
Federal Regulations (10 CFR), this means that operation of the facility 
in accordance with the proposed amendment would not (1) involve a 
significant increase in the probability or consequences of an accident 
previously evaluated, or (2) create the possibility of a new or 
different kind of accident from any accident previously evaluated; or 
(3) involve a significant reduction in a margin of safety. The basis 
for this proposed determination for each amendment request is shown 
below.
    The Commission is seeking public comments on this proposed 
determination. Any comments received within 30 days after the date of 
publication of this notice will be considered in making any final 
determination.
    Normally, the Commission will not issue the amendment until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment 
involves no significant hazards consideration. In addition, the 
Commission may issue the amendment prior to the expiration of the 30-
day comment period 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 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

[[Page 32769]]

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.

B. Electronic Submissions (E-Filing)

    All documents filed in NRC adjudicatory proceedings, including a 
request for hearing, a petition for leave to intervene, any motion or 
other document filed in the proceeding prior to the submission of a 
request for hearing or petition to intervene, and documents filed by 
interested governmental entities participating under 10 CFR 2.315(c), 
must be filed in accordance with the NRC's E-Filing rule (72 FR 49139; 
August 28, 2007). The E-Filing process requires participants to submit 
and serve all adjudicatory documents over the internet, or in some 
cases to mail copies on electronic storage media. Participants may not 
submit paper copies of their filings unless they seek an exemption in 
accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 
ten 10 days prior to the filing deadline, the participant should 
contact the Office of the Secretary by email at [email protected], 
or by telephone at 301-415-1677, to request (1) a digital 
identification (ID) certificate, which allows the participant (or its 
counsel or representative) to digitally sign documents and access the 
E-Submittal server for any proceeding in which it is participating; and 
(2) advise the Secretary that the participant will be submitting a 
request or petition for hearing (even in instances in which the 
participant, or its counsel or representative, already holds an NRC-
issued digital ID certificate). Based upon this information, the 
Secretary will establish an electronic docket for the hearing in this 
proceeding if the Secretary has not already established an electronic 
docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/getting-started.html. System requirements for accessing 
the E-Submittal server are detailed in the NRC's ``Guidance for 
Electronic Submission,'' which is available on the agency's public Web 
site at http://www.nrc.gov/site-help/e-submittals.html. Participants 
may attempt to use other software not listed on the Web site, but 
should note that the NRC's E-Filing system does not support unlisted 
software, and the NRC Meta System Help Desk will not be able to offer 
assistance in using unlisted software.
    If a participant is electronically submitting a document to the NRC 
in accordance with the E-Filing rule, the participant must file the 
document using the NRC's online, Web-based submission form. In order to 
serve documents through the Electronic Information Exchange System, 
users will be required to install a Web browser plug-in from the NRC's 
Web site. Further information on the Web-based submission form, 
including the installation of the Web browser plug-in, is available on 
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
    Once a participant has obtained a digital ID certificate and a 
docket has been created, the participant can then submit a request for 
hearing or petition for leave to intervene. Submissions should be in 
Portable Document Format (PDF) in accordance with NRC guidance 
available on the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the 
documents are submitted through the NRC's E-Filing system. To be 
timely, an electronic filing must be submitted to the E-Filing system 
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of 
a transmission, the E-Filing system time-stamps the document and sends 
the submitter an email notice confirming receipt of the document. The 
E-Filing system also distributes an email notice that provides access 
to the document to the NRC's Office of the General Counsel and any 
others who have advised the Office of the Secretary that they wish to 
participate in the proceeding, so that the filer need not serve the 
documents on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before a hearing request/petition 
to intervene is filed so that they can obtain access to the document 
via the E-Filing system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System 
Help Desk through the ``Contact Us'' link located on the NRC's public 
Web site at http://www.nrc.gov/site-help/e-submittals.html, by email to 
[email protected], or by a toll-free call at 1-866-672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., 
Eastern Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the

[[Page 32770]]

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, 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 
``Accessing Information and Submitting Comments'' section of this 
document.
PSEG Nuclear LLC, Docket Nos. 50-272 and 50-311, Salem Nuclear 
Generating Station, Units 1 and 2, Salem County, New Jersey
    Date of amendment request: March 24, 2014. A publicly-available 
version is in ADAMS under Accession No. ML14083A439.
    Description of amendment request: The proposed amendment would 
revise Salem Surveillance Requirements (SRs) 4.2.1.3, 4.2.1.4, and 
4.2.2.2.f associated with Power Distribution Limits Technical 
Specification (TS) 3/4.2.1, ``Axial Flux Difference (AFD),'' and TS 3/
4.2.2, ``Heat Flux Hot Channel Factor--FQ(Z).''
    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 change to Surveillance Requirement (SR) 4.2.1.3 will not 
result in any design or regulatory limit being exceeded with respect 
to the safety analyses documented in the Updated Final Safety 
Analysis Report (UFSAR). The change to SR 4.2.1.3 aligns the 
Technical Specifications (TS) with the current TS Bases and is 
consistent with NUREG-1431; there is no change to how target flux 
difference is measured. Since the change does not impact any 
conditions that would initiate an accident, the probability or 
consequences of previously analyzed events is not increased.
    Therefore, there is no impact to the probability or consequences 
of an accident previously evaluated.
    The change to SR 4.2.1.4 and TS Bases by utilizing the predicted 
Axial Flux Difference (AFD) at end of cycle life in determining the 
target AFD via interpolation will not result in any design or 
regulatory limit being exceeded with respect to the safety analyses 
documented in the UFSAR. The change to SR 4.2.1.4 aligns the TS with 
the Salem UFSAR design basis as described in Section 4. 3.2.2.6, 
which specifies use of cycle specific target values, and is 
consistent with NUREG-1431. Since the change does not impact any 
conditions that would initiate an accident, the probability or 
consequences of previously analyzed events is not increased.
    Therefore, there is no impact to the probability or consequences 
of an accident previously evaluated.
    The relocation of the SR 4.2.2.2.f axial exclusion zones to the 
TS Bases has no impact to the accidents analyzed in the Salem UFSAR 
and is not an accident initiator. The relocation of the axial 
exclusion zones to the TS Bases is consistent with NUREG-1431. Since 
the change does not impact any conditions that would initiate an 
accident, the probability or consequences of previously analyzed 
events is not increased.
    Therefore, there is no impact to 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 change to SR 4.2.1.3 will not result in any design or 
regulatory limit being exceeded with respect to the safety analyses 
documented in the UFSAR. The change to SR 4.2.1.3 aligns the TS with 
the current TS Bases and is consistent with NUREG-1431; there is no 
change to how target flux difference is measured. Since the change 
does not impact any conditions that would initiate an accident, 
there is no possibility of a new or different kind of accident 
resulting from the change.
    Therefore, there is no possibility of a new or different kind of 
accident from those previously evaluated.
    The change to SR 4.2.1.4 and TS Bases by utilizing the predicted 
Axial Flux Difference (AFD) at end of cycle life in determining the 
target AFD via interpolation will not result in any design or 
regulatory limit being exceeded with respect to the safety analyses 
documented in the UFSAR. The change to SR 4.2.1.4 aligns the TS with 
the Salem UFSAR design basis as described in Section 4.3.2.2.6, 
which specifies use of cycle specific target values, and is 
consistent with NUREG-1431. Since the change does not impact any 
conditions that would initiate an accident, there is no possibility 
of a new or different kind of accident resulting from the change.
    Therefore, there is no possibility of a new or different kind of 
accident from those previously evaluated.
    The relocation of the SR 4.2.2.2.f axial exclusion zones to the 
TS Bases has no impact to the accidents analyzed in the Salem UFSAR 
and is not an accident initiator. The relocation of the axial 
exclusion zones to the TS Bases is consistent with NUREG-1431. Since 
the change does not impact any conditions that would initiate an 
accident, there is no possibility of a new or different kind of 
accident resulting from the change.
    Therefore, there is no possibility of a new or different kind of 
accident from those previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The change to SR 4.2.1.3 will not result in any design or 
regulatory limit being exceeded with respect to the safety analyses 
documented in the UFSAR. The change to SR 4.2.1.3 aligns the TS with 
the current TS Bases and is consistent with NUREG-1431; there is no 
change to how target flux difference is measured.
    Therefore, there is no reduction in margin of safety.
    The change to SR 4.2.1.4 and TS Bases by utilizing the predicted 
Axial Flux Difference

[[Page 32771]]

(AFD) at end of cycle life in determining the target AFD via 
interpolation will not result in any design or regulatory limit 
being exceeded with respect to the safety analyses documented in the 
UFSAR. The change to SR 4.2.1.4 aligns the TS with the Salem UFSAR 
design basis as described in Section 4.3.2.2.6, which specifies use 
of cycle specific target values, and is consistent with NUREG-1431.
    Therefore, there is no reduction in margin of safety.
    The relocation of the SR 4.2.2.2.f axial exclusion zones to the 
TS Bases has no impact to the accidents analyzed in the Salem UFSAR 
and is not an accident initiator. The relocation of the axial 
exclusion zones to the TS Bases is consistent with NUREG-1431. In 
accordance with NRC approved methodologies (TS 6.9.1.9), reload 
specific safety evaluations are performed to ensure that the limits 
of safety analyses are met (i.e., margin of safety).
    Therefore, the relocation of the axial exclusion zones to the TS 
Bases does not impact margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.

    Attorney for licensee: Jeffrie J. Keenan, PSEG Nuclear LLC--N21, 
P.O. Box 236, Hancocks Bridge, NJ 08038.
    NRC Branch Chief: Meena K. Khanna.
South Carolina Electric and Gas Company, South Carolina Public Service 
Authority, Docket No. 50-395, Virgil C. Summer Nuclear Station (VCSNS), 
Unit 1, Fairfield County, South Carolina
    Date of amendment request: April 7, 2014. A publicly-available 
version is in ADAMS under Accession No. ML14122A144.
    Description of amendment request: The proposed amendment requests 
approval of a revision to the emergency action levels from a scheme 
based on NEI 99-01, Revision 5, ``Methodology for Development of 
Emergency Action Levels'' to a scheme based on NEI 99-01, Revision 6, 
``Methodology for Development of Emergency Action Levels.''
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes to the VCSNS emergency action levels do not 
impact the physical function of plant structures, systems, or 
components (SSC) or the manner in which SSCs perform their design 
function. The proposed changes neither adversely affect accident 
initiators or precursors, nor alter design assumptions. The proposed 
changes do not alter or prevent the ability of SSCs to perform their 
intended function to mitigate the consequences of an initiating 
event within assumed acceptance limits. No operating procedures or 
administrative controls that function to prevent or mitigate 
accidents are affected by the proposed changes.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed changes do not involve a physical alteration of the 
plant (i.e., no new or different type of equipment will be installed 
or removed) or a change in the method of plant operation. The 
proposed changes will not introduce failure modes that could result 
in a new accident, and the change does not alter assumptions made in 
the safety analysis. The proposed changes to the VCSNS emergency 
action levels are not initiators of any accidents.
    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 amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    Margin of safety is associated with the ability of the fission 
product barriers (i.e., fuel cladding, reactor coolant system 
pressure boundary, and containment structure) to limit the level of 
radiation dose to the public. The proposed changes do not impact 
operation of the plant or its response to transients or accidents. 
The changes do not affect the Technical Specifications or the 
operating license. The proposed changes do not involve a change in 
the method of plant operation, and no accident analyses will be 
affected by the proposed changes. Additionally, the proposed changes 
will not relax any criteria used to establish safety limits and will 
not relax any safety system settings. The safety analysis acceptance 
criteria are not affected by these changes. The proposed changes 
will not result in plant operation in a configuration outside the 
design basis. The proposed changes do not adversely affect systems 
that respond to safely shut down the plant and to maintain the plant 
in a safe shutdown condition. The emergency plan will continue to 
activate an emergency response commensurate with the extent of 
degradation of plant 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: J. Hagood Hamilton, Jr., South Carolina 
Electric & Gas Company, Post Office Box 764, Columbia, SC 29218.
    NRC Branch Chief: Robert J. Pascarelli.
Southern Nuclear Operating Company, Inc. Docket Nos. 52-025 and 52-026, 
Vogtle Electric Generating Plant, Units 3 and 4, Burke County, Georgia
    Date of amendment request: April 11, 2014. A publicly-available 
version is in ADAMS under Accession No. ML14101A459.
    Description of amendment request: The proposed license amendment 
request would depart from the plant-specific Design Control Document 
(DCD) Tier 1 and Tier 2 material to describe modifications to increase 
the efficiency of the return of condensate utilized by the passive core 
cooling system to the in-containment refueling water storage tank to 
support the capability for long-term cooling.
    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 containment condensate flow path changes provide 
sufficient condensate return flow to maintain In-containment 
Refueling Water Storage Tank (IRWST) level above the top of the 
Passive Residual Heat Removal Heat Exchanger (PRHR HX) tubes, thus 
preventing PRHR HX performance degradation from that considered in 
the safety analyses. The added components are seismically qualified 
and constructed of only those materials appropriately suited for 
exposure to the reactor coolant environment as described in [Updated 
Final Safety Analysis Report] UFSAR Section 6.1. No aluminum is 
permitted to be used in the construction of these components so that 
they do not contribute to hydrogen production in containment. The 
proposed changes do not alter design features available during 
anticipated operational occurrences or accidents. The proposed 
changes do not involve any accident initiating component/system 
failure or event, thus the probabilities of the accidents previously 
evaluated are not affected. The affected equipment does not 
adversely affect or interact with safety-related equipment or a 
radioactive material barrier, and this activity does not involve the 
containment of radioactive material. Thus, the proposed changes do 
not affect any

[[Page 32772]]

safety-related accident mitigating function. The radioactive 
material source terms and release paths used in the safety analyses 
are unchanged, thus the radiological releases in the UFSAR accident 
analyses are not affected.
    Therefore, the proposed amendment does not involve an 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 long-term safe shutdown analysis results show that the PRHR 
HX continues to meets its acceptance criterion, i.e., to cool the 
Reactor Coolant System (RCS) to below 420[deg]F in 36 hours. The 
affected equipment does not adversely interface with any component 
whose failure could initiate an accident, or any component that 
contains radioactive material. The modified components do not 
incorporate any active features relied upon to support normal 
operation. The downspout and gutter return components are 
seismically qualified to remain in place and functional during 
seismic and dynamic events. The containment condensate flow path 
changes do not create a new fault or sequence of events that could 
result in a radioactive material release.
    Therefore, the proposed amendment does not create the 
possibility of a new or different kind of accident.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed changes do not reduce the redundancy, diversity or 
performance of any safety-related function. The proposed containment 
condensate flow path changes provide sufficient condensate return 
flow to maintain adequate IRWST water level for those events using 
the PRHR HX cooling function. The long-term Shutdown Temperature 
Evaluation results show the PRHR HX continues to meets [sic] its 
acceptance criterion. The UFSAR Chapters 6 and 15 analyses results 
are not affected, thus margins to their regulatory acceptance 
criteria are unchanged. The added components are classified as 
safety-related, seismically qualified, and comply with their 
applicable design codes. No safety analysis or design basis 
acceptance limit/criterion is challenged or exceeded by the proposed 
changes, thus no margin of safety is reduced.
    Therefore, the proposed amendment does not reduce the margin of 
safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: M. Stanford Blanton, Balch & Bingham LLP, 
1710 Sixth Avenue North, Birmingham, AL 35203-2015.
    NRC Branch Chief: Lawrence J. Burkhart.

II. 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 
``Accessing Information and Submitting Comments'' section of this 
document.
PPL Susquehanna, LLC, Docket Nos. 50-387 and 50-388, Susquehanna Steam 
Electric Station, Units 1 and 2, Luzerne County, Pennsylvania
    Date of amendment request: June 6, 2013, as supplemented by letter 
dated January 23, 2014.
    Brief description of amendments: These amendments change 
Surveillance Requirement (SR) 3.5.1.12 in Technical Specification (TS) 
3.5.1, ``ECCS [emergency core cooling system]--Operating.'' 
Specifically, the amendments eliminate the TS requirement for the 
Automatic Depressurization System (ADS) valves to open during manual 
actuation of the ADS circuitry, change the surveillance frequency from 
``24 months on a STAGGERED TEST BASIS for each valve solenoid,'' to 
``24 months,'' and remove a note above the SR that stated the SR was 
``not required to be performed until 12 hours after reactor steam 
pressure and flow are adequate to perform the test.''
    Date of issuance: May 14, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment Nos.: 260 and 241. A publicly-available version is in 
ADAMS under Accession No. ML14111A052; documents related to these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Renewed Facility Operating License Nos. NPF-14 and NPF-22: The 
amendments revised the license and the TS.
    Date of initial notice in Federal Register: December 10, 2013 (78 
FR 74183). The supplemental letter dated January 23, 2014, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated May 14, 2014.
    No significant hazards consideration comments received: No.
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, Units 1 and 2, Appling County, Georgia
    Date of amendment request: July 5, 2012, as supplemented by letters 
dated November 13 and November 30, 2012, and February 22, 2013.
    Brief description of amendments: The amendments revise the 
Technical Specification Limiting Condition for Operation for the plant 
service water (PSW) and ultimate heat sink. Specifically, the 
surveillance requirement for the minimum water level in each PSW pump 
well of the intake structure would be revised from a value of 60.7 feet 
mean sea level (MSL) to a value of 60.5 MSL.
    Date of issuance: May 13, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.

[[Page 32773]]

    Amendment Nos.: Unit 1-267 and Unit 2-211. A publicly-available 
version is in ADAMS under Accession No. ML14042A465; documents related 
to these amendments are listed in the Safety Evaluation enclosed with 
the amendments.
    Renewed Facility Operating License Nos. DPR-57 and NPF-5: 
Amendments revised the licenses and the technical specifications.
    Date of initial notice in Federal Register: September 4, 2012 (77 
FR 53930). The supplements dated November 13, and November 30, 2012, 
and February 22, 2013, 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 May 13, 2014.
    No significant hazards consideration comments received: No.
Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50-
364, Joseph M. Farley Nuclear Plant, Units 1 and 2, Houston County, 
Alabama
    Date of amendment request: December 21, 2012, as supplemented by 
letter dated May 21, 2013.
    Brief description of amendment request: The amendments will 
incorporate a degraded grid voltage modification schedule into the J. 
M. Farley operating licenses. This modification would eliminate the 
need for manual actions in the event of a degraded grid voltage 
condition.
    Date of issuance: May 13, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos.: 194 and 190. A publicly-available version is in 
ADAMS under Accession No. ML14069A344; documents related to this these 
amendments are listed in the Safety Evaluation enclosed with the 
amendments.
    Renewed Facility Operating License Nos. NPF-2 and NPF-8: Amendment 
revised the Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: September 3, 2013 (78 
FR 54289). The supplement dated May 21, 2013, 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 
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 May 13, 2014.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 30th day of May, 2014.

    For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2014-13217 Filed 6-5-14; 8:45 am]
BILLING CODE 7590-01-P