Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 21294-21301 [2014-08219]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 79, Number 72 (Tuesday, April 15, 2014)]
[Notices]
[Pages 21294-21301]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-08219]


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NUCLEAR REGULATORY COMMISSION

[NRC-2014-0082]


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 March 20, 2014, to April 2, 2014. The last 
biweekly notice was published on April 1, 2014.

DATES: Comments must be filed by May 15, 2014. A request for a hearing 
must be filed by June 16, 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 https://www.regulations.gov and search for Docket ID NRC-2014-0082. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. 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-06-44M, 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: Angela Baxter, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-2976, email: angela.baxter@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Accessing Information and Submitting Comments.

A. Accessing Information

    Please refer to Docket ID NRC-2014-0082 when contacting the NRC 
about the availability of information regarding this document. You may 
access publicly-available information related to this document by any 
of the following methods:
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2014-0082.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. 
Documents may be viewed in ADAMS by performing a search on the document 
date and docket number.
     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-2014-0082 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 you 
comment submission. The NRC will post all comment submissions at https://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

[[Page 21295]]

Hazards Consideration Determination, any hearing will take place after 
issuance. The Commission expects that the need to take this action will 
occur very infrequently.

A. Opportunity To Request a Hearing and Petition for Leave To Intervene

    Within 60 days after the date of publication of this notice, any 
person(s) whose interest may be affected by this action may file a 
request for a hearing and a petition to intervene with respect to 
issuance of the amendment to the subject facility operating license or 
combined license. Requests for a hearing and a petition for leave to 
intervene shall be filed in accordance with the Commission's ``Agency 
Rules of Practice and Procedure'' in 10 CFR Part 2. Interested 
person(s) should consult a current copy of 10 CFR 2.309, which is 
available at the NRC's PDR, located at One White Flint North, Room O1-
F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. The 
NRC's regulations are accessible electronically from the NRC Library on 
the NRC's Web site at https://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to intervene is 
filed 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.

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

[[Page 21296]]

    Once a participant has obtained a digital ID certificate and a 
docket has been created, the participant can then submit a request for 
hearing or petition for leave to intervene. Submissions should be in 
Portable Document Format (PDF) in accordance with NRC guidance 
available on the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the 
documents are submitted through the NRC's E-Filing system. To be 
timely, an electronic filing must be submitted to the E-Filing system 
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of 
a transmission, the E-Filing system time-stamps the document and sends 
the submitter an email notice confirming receipt of the document. The 
E-Filing system also distributes an email notice that provides access 
to the document to the NRC's Office of the General Counsel and any 
others who have advised the Office of the Secretary that they wish to 
participate in the proceeding, so that the filer need not serve the 
documents on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before a hearing request/petition 
to intervene is filed so that they can obtain access to the document 
via the E-Filing system.
    A person filing electronically using the NRC's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System 
Help Desk through the ``Contact Us'' link located on the NRC's public 
Web site at https://www.nrc.gov/site-help/e-submittals.html, by email to 
MSHD.Resource@nrc.gov, or by a toll-free call at 866-672-7640. The NRC 
Meta System Help Desk is available between 8 a.m. and 8 p.m., Eastern 
Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland, 20852, Attention: Rulemaking and Adjudications Staff. 
Participants filing a document in this manner are responsible for 
serving the document on all other participants. Filing is considered 
complete by first-class mail as of the time of deposit in the mail, or 
by courier, express mail, or expedited delivery service upon depositing 
the document with the provider of the service. A presiding officer, 
having granted an exemption request from using E-Filing, may require a 
participant or party to use E-Filing if the presiding officer 
subsequently determines that the reason for granting the exemption from 
use of E-Filing no longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
https://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the 
Commission, or the presiding officer. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law 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.

Entergy Operations, Inc., Docket No. 50-368, Arkansas Nuclear One, Unit 
2, Pope County, Arkansas

    Date of amendment request: January 21, 2014, as supplemented by 
letter dated March 17, 2014. A publicly-available version is in ADAMS 
under Accession Nos. ML14021A085 and ML14077A139.
    Description of amendment request: The amendment would modify 
Technical Specification (TS) 6.5.16, ``Containment Leakage Rate Testing 
Program,'' to require a seal contact verification in lieu of a seal 
pressure test with respect to the Emergency Escape Air Lock doors.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change would permit Emergency Escape Air Lock door 
seal leak rate testing to be performed by a seal contact check 
following door opening, overall full pressure test of the Emergency 
Escape Air Lock, or seal contact adjustments. The seal contact test 
method will result in a continuation of the established practice 
which has provided a high degree of confidence in door seal 
performance. At Palisades [Nuclear Plant,] Emergency Escape Air Lock 
door seals which have been inspected in accordance with the proposed 
methodology have passed subsequent full pressure Emergency Escape 
Air Lock leakage tests and have not interfered with successful 
Containment Building Integrated Leak Rate Testing (ILRT).
    Since the proposed methodology can be used to successfully 
verify door seal condition and contact, the use of this methodology 
for testing will not cause an increase in the probability of a 
leaking Emergency Escape Air Lock door seal going undetected. The 
combination of the door seal contact check and the overall full 
pressure testing of the Emergency Escape Air Lock will provide high 
confidence of the air lock performing its design function under 
accident conditions.
    Therefore, this 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 is associated exclusively with testing of 
features related to Containment Building integrity. The change 
affects only the testing methodology of the Emergency Escape Air 
Lock door seals. The

[[Page 21297]]

proposed testing method does not result in any physical alterations 
to the plant configuration, no new structure, system, or component 
(SSC) is added, no SSC interfaces are modified, and no changes to 
any design function of an SSC or the methods of SSC operation are 
being made. As the proposed change would not change the design, 
configuration, or operation of the plant, the change would not cause 
the Containment Leakage Rate Testing Program to become an accident 
initiator.
    Therefore, this change 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.
    The proposed change is associated exclusively with testing of 
features related to Containment Building integrity. The change 
affects only the testing methodology of the Emergency Escape Air 
Lock door seals. The change is unrelated to an initiator of any 
accident previously evaluated. The proposed application of a door 
seal contact check in lieu of a between-the-seals pressure test 
along with continuation of the overall full pressure test of the 
Emergency Escape Air Lock will continue to provide high confidence 
that the Containment Building leakage rate criteria for the 
Emergency Escape Air Lock will not exceed the maximum allowable 
leakage rates defined in the TSs or assumed in the accident 
analysis.
    Therefore, this change does not involve a significant reduction 
in a margin 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: Joseph A. Aluise, Associate General Counsel-
Nuclear, Entergy Services, Inc., 639 Loyola Avenue, New Orleans, 
Louisiana 70113.
    NRC Branch Chief: Michael T. Markley.

Entergy Nuclear Operations, Inc., Docket No. 50-333, James A. 
FitzPatrick Nuclear Power Plant (JAFNPP), Oswego County, New York

    Date of amendment request: May 7, 2013. A publicly-available 
version is in ADAMS under Accession No. ML13128A165.
    Description of amendment request: The proposed amendment would 
revise JAFNPP's Renewed Facility Operating License (RFOL) Condition 2.T 
wording to be congruent with the proposed license condition wording 
contained in NUREG-1905 SER Section 1.7 and to clarify that the 
programs and activities described in the Updated Final Safety Analysis 
Report (UFSAR) Supplement (and identified in Appendix A of NUREG-1905) 
are to be completed no later than the period of extended operation 
date. The change removes any potential inference that any of the 
activities are being implemented after the period of extended 
operation. The intent of this proposed amendment is to ensure that (1) 
the changes made to these programs and activities are made in 
accordance with the 10 CFR 50.59 process, and clarify that (2) only the 
changes to the implementation date of those license renewal commitments 
that have been codified by inclusion into the UFSAR are required to be 
made in accordance with the 10 CFR 50.90 process.
    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:

    4.1.1 Does the proposed amendment involve a significant increase 
in the probability or consequences of an accident previously 
evaluated?
    No, the proposed amendment does not involve a change to a 
System, Structure, or Component (SSC) that initiates a plant 
accident. The change clarifies JAFNPP RFOL Condition 2.T. The 
license condition deals with the administrative controls over 
information contained in the Updated Final Safety Analysis Report 
(UFSAR) supplement. In addition, the change provides the actual 
completion date in lieu of the schedule contained in the Commitment 
Appendix of the SER, for license renewal commitments codified into 
the UFSAR and removes the inference that any programs and activities 
are being implemented during the period of extended operation. The 
proposed changes are administrative and the license condition does 
not initiate or mitigate any previously evaluated accidents.
    Therefore, the proposed amendment does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    4.1.2 Does the proposed amendment create the possibility of a 
new or different kind of accident from any accident previously 
evaluated?
    No, the proposed amendment does not involve any physical 
alteration of plant equipment and does not change the method by 
which any safety-related system performs its function. The license 
condition deals with the administrative controls over information 
contained in the UFSAR supplement. In addition, the change provides 
the actual completion date in lieu of the schedule contained in the 
Commitment Appendix of the SER, for license renewal commitments 
codified into the UFSAR and removes the inference that any 
activities are being implemented during the period of extended 
operation. No new or different types of equipment will be installed 
and the basic operation of installed equipment is unchanged.
    Therefore, the proposed amendment does not create the 
possibility of a new or different kind of accident from any accident 
previously evaluated.
    4.1.3: Does the proposed amendment involve a significant 
reduction in a margin of safety?
    No, the proposed amendment does not affect design codes or 
design margins. The changes that clarifies JAFNPP RFOL Condition 2.T 
are administrative in nature and do not have the ability to affect 
any analyzed safety margins.
    Therefore, operation of JAFNPP in accordance with the proposed 
amendment change will not involve a significant reduction in the 
margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Jeanne Cho, Assistant General Counsel, 
Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, NY 
10601.
    NRC Branch Chief: Benjamin G. Beasley.

Entergy Nuclear Operations, Inc., Docket No. 50-255, Palisades Nuclear 
Plant, Van Buren County, Michigan

    Date of amendment request: December 30, 2013. A publicly available 
version is in ADAMS under Accession No. ML13364A328.
    Description of amendment request: The proposed amendment would 
change the Palisades Nuclear Plant (PNP) Cyber Security Plan (CSP) 
Milestone 8 full implementation date as set forth in the Cyber Security 
Plan Implementation Schedule approved by Amendment No. 243 issued on 
July 28, 2011, to Renewed Facility Operating License No. DPR-20 for PNP 
(ADAMS Accession No. ML111801243).
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change to the CSP Implementation Schedule is 
administrative in nature. This change does not alter accident 
analysis assumptions, add any initiators, or affect the function of 
plant systems or the manner in which systems are operated, 
maintained, modified, tested, or inspected.

[[Page 21298]]

The proposed change does not require any plant modifications which 
affect the performance capability of the structures, systems, and 
components relied upon to mitigate the consequences of postulated 
accidents, and has no impact on the probability or consequences of 
an accident previously evaluated.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed change to the CSP Implementation Schedule is 
administrative in nature. This proposed change does not alter 
accident analysis assumptions, add any initiators, or affect the 
function of plant systems or the manner in which systems are 
operated, maintained, modified, tested, or inspected. The proposed 
change does not require any plant modifications which affect the 
performance capability of the structures, systems and components, 
relied upon to mitigate the consequences of postulated accidents and 
does not create the possibility of a new or different kind of 
accident from any accident previously evaluated.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    Plant safety margins are established through limiting conditions 
for operation, limiting safety system settings, and safety limits 
specified in the technical specifications. The proposed change to 
the CSP Implementation Schedule is administrative in nature. In 
addition, the milestone date delay for full implementation of the 
CSP has no substantive impact because other measures have been taken 
which provide adequate protection during this period of time. 
Because there is no change to established safety margins as a result 
of this change, the proposed change does not involve a significant 
reduction in a margin of safety.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: William Dennis, Assistant General Counsel, 
Entergy Nuclear Operations, Inc., 440 Hamilton Ave., White Plains, NY 
10601.
    NRC Branch Chief: Robert D. Carlson.

FirstEnergy Nuclear Operating Company, et al., Docket No. 50-440, Perry 
Nuclear Power Plant, Unit 1, Lake County, Ohio

    Date of amendment request: December 6, 2013, as supplemented by a 
letter dated. February 27, 2014. A publicly-available version is in 
ADAMS under Accession Nos. ML13343A013 and ML14059A221.
    Description of amendment request: The proposed amendment would 
revise the Updated Safety Analyses Report (USAR) to reflect updated 
radiological calculations using an alternative accident source term 
(AST) from the applicable design bases event and to revise the 
technical specification (TS) definition of DOSE EQUIVALENT IODINE-131.
    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. This proposed amendment does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    The proposed amendment involves implementation of the AST for 
the control rod drop accident (CRDA) and the main steam line break 
(MSLB) at PNPP. The proposed amendment also updates the methods and 
assumptions used in the loss of coolant accident (LOCA) dose 
calculation, which maintains conformance with Regulatory Guide (RG) 
1.183, and revises the TS DOSE EQUIVALENT 1-131 definition. The 
proposed amendment does not involve any physical design 
modifications to plant structures, systems or components other than 
the planned use of GNF2 fuel beginning with Cycle 16, and the 
revised calculations do not impact any accident initiators. Because 
design basis accident initiators are not being altered, the 
probability of an accident previously evaluated is not affected.
    With respect to consequences, the AST is an input to 
calculations used to evaluate the consequences of an accident, and 
that AST input does not by itself affect the plant response, or the 
actual path of radiation postulated to be released. The design basis 
radiological consequence analyses themselves, which include updates 
to the core source term, input assumptions, and the methodology used 
to calculate dose consequences, do not affect the plant response, or 
the actual pathway of radiation that might be released during an 
event. Likewise, the DOSE EQUIVALENT 1-131 definition revision does 
not affect any plant response. For the evaluated events and the 
definition revision, the analyses demonstrate acceptable doses 
within regulatory limits. As detailed in the technical evaluation 
for the amendment request, a comparison of the former dose 
consequences against the newly calculated dose consequences for the 
evaluated events showed that the doses at the EAB and the LPZ are 
either negligibly changed or are lower than previously evaluated, 
except for the CRDA Scenario 1 analysis, for which the calculated 
doses increase, but by less than 2 percent of the margin to the 
acceptance criteria. The acceptance criteria for the CRDA is 
specified in RG-1.183 Table 6, and is only 25 percent of the 
regulatory limit specified in 10 CFR 50.67. Control room doses for 
the LOCA event decrease; for the other events, control room doses 
were not previously required to be calculated. Therefore, it is 
concluded that the consequences of previously evaluated accidents 
are not significantly increased.
    Based on the above conclusions, this proposed amendment does not 
involve a significant increase in the probability or consequences of 
an accident previously evaluated.
    2. This proposed amendment does not create the possibility of a 
new or different kind of accident from any accident previously 
evaluated.
    The proposed amendment does not involve a physical alteration of 
the plant. No new or different type of equipment will be installed 
and there are no physical modifications to existing installed 
equipment associated with the proposed changes. Also, there are no 
proposed changes to the methods governing plant/system operation, so 
no new initiators or precursors of a new or different kind of 
accident are created. New equipment or personnel failure modes that 
might initiate a new type of accident are not created as a result of 
the proposed amendment.
    Thus, this amendment does not create the possibility of a new or 
different kind of accident from any accident previously evaluated.
    3. This proposed amendment does not involve a significant 
reduction in a margin of safety.
    Approval is requested for changes that primarily conform with 
RG-1.183 for the CRDA, MSLB, and LOCA analyses, as well as the TS 
DOSE EQUIVALENT 1-131 definition. The results of the accident 
analyses, including the use of FGR 11 dose conversion factors, are 
subject to acceptance criteria specified in 10 CFR 50.67 ``Accident 
source term,'' and RG-1.183. The analyses have been performed using 
conservative methodologies, as specified in RG-1.183. Safety margins 
have been evaluated and analytical conservatism has been utilized to 
ensure the analyses adequately bound postulated event scenarios. The 
dose consequences remain within the acceptance criteria presented in 
10 CFR 50.67 ``Accident source term,'' and RG-1.183. The only 
calculated doses that were determined to increase did so by less 
than 2 percent of the margin to the acceptance criteria specified in 
RG-1.183 (the regulatory guide acceptance criteria are 25 percent of 
the regulatory limits specified in 10 CFR 50.67).
    Therefore the proposed license amendment does not involve a 
significant reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are

[[Page 21299]]

satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: David W. Jenkins, Attorney, FirstEnergy 
Corporation, Mail Stop. A-GO-15, 76 South Main Street, Akron, OH 44308.
    NRC Branch Chief: Travis L. Tate.

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

    Date of amendment request: September 5, 2013. A publicly-available 
version is in ADAMS under Accession No. ML13249A242.
    Description of amendment request: The proposed amendment would 
relocate the operability and surveillance requirements for flood 
protection from the Hope Creek Generating Station (Hope Creek) 
Technical Specifications (TS) to the Hope Creek Technical Requirements 
Manual (TRM).
    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 with the NRC staff's edits in 
square brackets:

    1. Do the proposed changes involve a significant increase in the 
probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed changes to the TS would relocate the operability 
and surveillance requirements for the flood protection from the TS 
to the TRM. Flood protection is not assumed to be an initiator of an 
accident in the Hope Creek UFSAR [Updated Final Safety Analysis 
Report]. The proposed changes do not alter the design of any system, 
structure, or component (SSC). The proposed changes conform to NRC 
regulatory [requirements] regarding the content of plant TS, as 
identified in 10 CFR 50.36, [and the regulatory guidance identified 
in] NUREG-1433, and [also conform with] the NRC's Final Policy 
Statement published on July 22, 1993 (58 FR 39132).
    Therefore, these proposed changes do not represent a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Do the proposed changes create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed changes to the TS would relocate the operability 
and surveillance requirements for flood protection from the TS to 
the TRM. The proposed changes do not involve a modification to the 
physical configuration of the plant or a change in the methods 
governing normal plant operation. The proposed changes will not 
impose any new or different requirement or introduce a new accident 
initiator, accident precursor, or malfunction mechanism.
    Additionally, there is no change in the types or increases in 
the amounts of any effluent that may be released off-site and there 
is no increase in individual or cumulative occupational exposure.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from any accident previously 
evaluated.
    3. Do the proposed changes involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed changes to the TS would relocate the operability 
and surveillance requirements for flood protection from the TS to 
the TRM. This relocation will not affect protection criteria for 
plant equipment and will not reduce the margin of safety.
    Operability and surveillance requirements will be established in 
a licensee-controlled document, the TRM, to ensure the capability 
for external flood protection remains intact. Changes to these 
requirements in the TRM will be subject to the provisions of 10 CFR 
50.59, providing an appropriate level of regulatory control.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, and with the changes noted above in square brackets, 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 Docket Nos.: 52-027 and 52-028, Virgil 
C. Summer Nuclear Station (VCSNS) Units 2 and 3, Fairfield County, 
South Carolina

    Date of amendment request: February 27, 2014. A publicly-available 
version is in ADAMS under Accession No. ML14065A022.
    Description of amendment request: The proposed change would amend 
Combined License Nos. NPF-93 and NPF-94 for the Virgil C. Summer 
Nuclear Station (VCSNS) Units 2 and 3 by departing from the plant-
specific Design Control Document (DCD) Tier 1 (and corresponding 
Combined License Appendix C information) and Tier 2 material by making 
changes to the annex and radwaste building structures and layout by:
    (1) Updating the annex building column line designations on 
affected Tier 1 Figures and Tier 2 Figure 3.7.2-19; and
    (2) Revising the radwaste building configuration including the 
shielding design and radiation area monitoring.
    Because, this proposed change requires a departure from Tier 1 
information in the Westinghouse Advanced Passive 1000 DCD, the licensee 
also requested an exemption from the requirements of the Generic DCD 
Tier 1 in accordance with 52.63(b)(1).
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed annex building changes updating column line 
designations and the radwaste building change to add three bunkers 
for storage of moderate and high activity waste, incorporate the 
Waste Accumulation Room and the Packaged Waste Storage Room, revise 
shield wall thicknesses, and eliminate a radiation monitor no longer 
needed do not alter the assumed initiators to any analyzed event. 
These proposed changes do not affect the operation of any systems or 
equipment that could initiate an analyzed accident. The proposed 
changes to the annex building column line designations update the 
annex building column line designations in the UFSAR figures to make 
them consistent with the UFSAR figure for the auxiliary building. 
The radwaste building proposed changes do not affect any accident 
initiators, because there is no accident initiator located within 
that building. Based on the above, the probability of an accident 
previously evaluated will not be increased by these proposed 
changes.
    The proposed annex and radwaste building configuration changes 
do not affect any radiological dose consequence analysis for UFSAR 
Chapter 15. No accident source term parameter or fission product 
barrier is impacted by these changes. Structures, systems, and 
components (SSCs) required for mitigation of analyzed accidents are 
not affected by these changes, and the functions of these buildings 
are not adversely affected by these changes. Consequently, this 
activity will not increase the consequences of any analyzed 
accident, including the main steam line limiting break.
    Therefore, the proposed activity does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed annex building changes updating column line 
designations and the radwaste building change to add three bunkers 
for storage of moderate and high

[[Page 21300]]

activity waste, incorporate the Waste Accumulation Room and the 
Packaged Waste Storage Room, revise shield wall thicknesses, and 
eliminate a radiation monitor no longer needed do not change the 
design function of the either of these buildings or any of the 
systems or equipment contained therein or in any other Nuclear 
Island structures. These proposed changes do not adversely affect 
any system design functions or methods of operation. These changes 
do not introduce any new equipment or components or change the 
operation of any existing systems or equipment in a manner that 
would result in a new failure mode, malfunction, or sequence of 
events that could affect safety-related or non-safety-related 
equipment or result in a radioactive material release. This activity 
does not allow for a new radioactive material release path or result 
in a new radioactive material barrier failure mode.
    Therefore, this activity does not create the possibility of a 
new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed changes do not affect any safety-related equipment, 
design code compliance, design function, design analysis, safety 
analysis input or result, or design/safety margin. The margin in the 
design of the annex and radwaste buildings is determined by the use 
of the current codes and standards and adherence to the assumptions 
used in the analyses of this structure and the events associated 
with this structure. The column line designations for the annex 
building in UFSAR Tier 2 figures are updated to make them consistent 
with the UFSAR figures for the auxiliary building. This change has 
no adverse impact on plant construction or operation. The design of 
the radwaste building, including the newly added bunkers for 
moderate and high activity waste, merging of the Waste Accumulation 
Room and the Packaged Waste Storage Room, will continue to be in 
accordance with the same codes and standards as stated in the UFSAR. 
The activity has no effect on off-site dose analysis for analyzed 
accidents.
    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: Kathryn M. Sutton, Morgan, Lewis & Bockius 
LLC, 1111 Pennsylvania Avenue NW., Washington, DC 20004-2514.
    NRC Branch Chief: Lawrence Burkhart.

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

    During the period since publication of the last biweekly notice, 
the Commission has issued the following amendments. The Commission has 
determined for each of these amendments that the application complies 
with the standards and requirements of the Atomic Energy Act of 1954, 
as amended (the Act), and the Commission's rules and regulations. The 
Commission has made appropriate findings as required by the Act and the 
Commission's rules and regulations in 10 CFR Chapter I, which are set 
forth in the license amendment.
    A notice of consideration of issuance of amendment to facility 
operating license or combined license, as applicable, proposed no 
significant hazards consideration determination, and opportunity for a 
hearing in connection with these actions, was published in the Federal 
Register as indicated.
    Unless otherwise indicated, the Commission has determined that 
these amendments satisfy the criteria for categorical exclusion in 
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), 
no environmental impact statement or environmental assessment need be 
prepared for these amendments. If the Commission has prepared an 
environmental assessment under the special circumstances provision in 
10 CFR 51.22(b) and has made a determination based on that assessment, 
it is so indicated.
    For further details with respect to the action see (1) the 
applications for amendment, (2) the amendment, and (3) the Commission's 
related letter, Safety Evaluation and/or Environmental Assessment as 
indicated. All of these items can be accessed as described in the 
``Accessing Information and Submitting Comments'' section of this 
document.

Calvert Cliffs Nuclear Power Plant, LLC, Docket Nos. 50-317, 50-318, 
and 72-8, Calvert Cliffs Nuclear Power Plant, Units 1 and 2, Calvert 
County, Maryland

Nine Mile Point Nuclear Station, LLC, Docket No. 50-220 and 50-410, 
Nine Mile Point Nuclear Station, Units 1 and 2, Oswego County, New York

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

    Date of amendment request: August 6, 2013, as supplemented by 
letters and emails dated August 14, 2013, September 23, 2013, September 
26, 2013, December 17, 2013, January 9, 2014, February 5, 2014, 
February 10, 2014, February 14, 2014, and February 21, 2014.
    Brief description of amendments: The amendments conform the 
licenses to reflect the direct transfer of operating authority for 
Calvert Cliffs Nuclear Power Plant, (Calvert Cliffs) Units 1 and 2, the 
Calvert Cliffs Independent Spent Fuel Storage Installation (ISFSI), 
Nine Mile Point Nuclear Station (Nine Mile Point), Units 1 and 2, and 
R.E. Ginna Nuclear Power Plant (Ginna) to Exelon Generation Company, 
LLC, as approved by the Commission Order dated March 24, 2014.
    Date of issuance: April 1, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment Nos.: Calvert Cliffs--305 and 283, Calvert Cliffs ISFSI--
10, Nine Mile Point--214 and 144, and Ginna--115. (ADAMS Accession Nos. 
ML14091A297, ML14091A323 and ML14091A366; documents related to these 
amendments are listed in the Safety Evaluation referenced in this 
notice).
    Renewed Facility Operating License Nos. DPR-53, DPR-69, SNM-2505, 
DPR-63. NPF-69, and DPR-18: The amendments revised the Licenses and 
Technical Specifications.
    Date of initial notice in Federal Register: December 26, 2013 (78 
FR 78411).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation for Calvert Cliffs dated March 24, 2014, and for 
Nine Mile Point and Ginna dated March 25, 2014.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. 50-352 and 50-353, Limerick 
Generating Station, Units 1 and 2, Montgomery County, Pennsylvania

    Date of application for amendments: April 9, 2013.
    Brief description of amendments: The amendments delete certain 
reporting requirements contained in the Technical Specifications (TSs).
    Date of issuance: March 26, 2014.
    Effective date: As of the date of issuance, to be implemented 
within 60 days.
    Amendments Nos.: 211 and 172. (ADAMS Accession No. ML13214A092; 
documents related to these amendments are listed in the Safety 
Evaluation referenced in this notice).
    Facility Operating License Nos. NPF-39 and NPF-85: The amendments 
revised the Facility Operating Licenses and the TSs.

[[Page 21301]]

    Date of initial notice in Federal Register: May 14, 2013 (78 FR 
28252).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated March 26, 2014.
    No significant hazards consideration comments received: No.

FirstEnergy Nuclear Operating Company, et al., Docket No. 50-346, 
Davis-Besse Nuclear Power Station, Unit 1, Ottawa County, Ohio

    Date of application for amendment: January 18, 2013, as 
supplemented by letters dated September 27, and December 13, 2013, and 
January 10, 2014.
    Brief description of amendment: This amendment revises Davis-Besse 
Nuclear Power Station (DBNPS) Technical Specification (TS) 3.4.17, 
``Steam Generator (SG) Tube Integrity''; TS 3.7.18, ``Steam Generator 
Level''; TS 5.5.8, ``Steam Generator (SG) Program''; and TS 5.6.6, 
``Steam Generator Tube Inspection Report.'' The revision to these TSs 
is to support plant operations following the replacement of the 
original SGs which is scheduled to be completed in April 2014. The 
changes to TS 3.4.17, TS 5.5.8, and TS 5.6.6 impose requirements that 
reflect the analysis and tube materials of the replacement SGs. These 
changes are consistent with Technical Specifications Task Force (TSTF) 
traveler TSTF-510, Revision 2, ``Revision to Steam Generator Program 
Inspection Frequencies and Tube Sample Selection,'' which was approved 
by the NRC on October 27, 2011. The revisions to TS 5.5.8 also include 
minor editorial changes and eliminates the requirements for special 
visual inspections of the internal auxiliary feedwater header, since 
this component will not be part of the replacement SGs.
    The changes to TS 3.7.18 impose inventory limits on the secondary-
side that reflect the design characteristics and dimensions of the 
replacement SGs. The revised limits will ensure that plant operations 
with the replacement SGs is bounded by the values used in the existing 
main steam line break analysis presented in the DBNPS Updated Safety 
Analysis Report.
    Date of issuance: March 31, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days.
    Amendment No.: 287. (ADAMS Accession No. ML14023A766; documents 
related to this amendment are listed in the Safety Evaluation 
referenced in this notice).
    Facility Operating License No. NPF-3: Amendment revised the 
Technical Specifications and License.
    Date of initial notice in Federal Register: March 19, 2013 (78 FR 
16883). The September 27, and December 13, 2013, and January 10, 2014, 
supplements contained clarifying information within the scope of the 
proposed action noticed and did not change the staff's initial proposed 
finding of no significant hazards consideration.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated March 31, 2014.
    No significant hazards consideration comments received: No.

Florida Power and Light Company, Docket No. 50-335, St. Lucie Plant 
Unit 1, St. Lucie County, Florida

    Date of application for amendment: May 10, 2013, as supplemented by 
letter dated September 30, 2013.
    Brief description of amendment: The amendment revises the Technical 
Specifications (TSs) to allow the use of AREVA M5[supreg] material as 
an approved fuel rod cladding.
    Date of issuance: March 31, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days of issuance.
    Amendment No.: 218. (ADAMS Accession No. ML14064A129; documents 
related to this amendment are listed in the Safety Evaluation 
referenced in this notice).
    Renewed Facility Operating License No. DPR-67: Amendment revises 
the license and the TSs.
    Date of initial notice in Federal Register: August 6, 2013 (78 FR 
47790). The September 30, 2013, supplemental letter provided additional 
information that clarified the application, did not expand the scope of 
the proposed amendment as originally noticed, and did not change the 
initial 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 March 31, 2014.
    No significant hazards consideration comments received: No.

Northern States Power Company--Minnesota (NSPM), Docket No. 50-263, 
Monticello Nuclear Generating Plant (MNGP), Wright County, Minnesota

    Date of application for amendment: January 21, 2010, as 
supplemented by letters dated March 4, 2010, September 28, 2010, 
November 11, 2011, June 27, 2012, September 28, 2012, November 30, 
2012, December 21, 2012, March 21, 2013, May 13, 2013, June 26, 2013, 
July 8, 2013, July 31, 2013, August 14, 2013, October 4, 2013, December 
20, 2013, and February 24, 2014.
    Brief description of amendment: The amendment revises the MNGP 
technical specifications to allow plant operation from the currently 
licensed Maximum Extended Load Line Limit Analysis (MELLLA) operating 
domain to operation in the expanded MELLLA Plus (MELLLA+) operating 
domain under the current extended power uprate conditions of 2004 
megawatts thermal rated core thermal power.
    Date of issuance: March 28, 2014.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days of issuance.
    Amendment No: 180. (ADAMS Accession No. ML14070A042; documents 
related to this amendment are listed in the Safety Evaluation 
referenced in this notice).
    Renewed Facility Operating License No. DPR-22: The amendment 
revised the Renewed Facility Operating License and Technical 
Specifications.
    Date of initial notice in Federal Register: September 21, 2010 (75 
FR 57527). The supplemental letters dated March 4, 2010, September 28, 
2010, November 11, 2010, June 27, 2012, September 28, 2012, November 
30, 2012, December 21, 2012, March 21, 2013, May 13, 2013, June 26, 
2013, July 8, 2013, July 31, 2013, August 14, 2013, October 4, 2013, 
December 20, 2013, and February 24, 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 
initial 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 March 28, 2014.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 4th day of April 2014.
    For the Nuclear Regulatory Commission.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2014-08219 Filed 4-14-14; 8:45 am]
BILLING CODE 7590-01-P