Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 76078-76089 [2012-30777]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 77, Number 247 (Wednesday, December 26, 2012)]
[Notices]
[Pages 76078-76089]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-30777]


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NUCLEAR REGULATORY COMMISSION

[NRC-2012-0305]


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

Background

    Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as 
amended (the Act), the U.S. Nuclear Regulatory Commission (the 
Commission or NRC) is publishing this regular biweekly notice. The Act 
requires the Commission publish notice of any amendments issued, or 
proposed to be issued and grants the Commission the authority to issue 
and make immediately effective any amendment to an operating license or 
combined license, as applicable, upon a determination by the Commission 
that such amendment involves no significant hazards consideration, 
notwithstanding the pendency before the Commission of a request for a 
hearing from any person.
    This biweekly notice includes all notices of amendments issued, or 
proposed to be issued from November 29, 2012 to December 12, 2012. The 
last biweekly notice was published on December 11, 2012 (77 FR 73684-
73694).

ADDRESSES: You may access information and comment submissions related 
to this document, which the NRC possesses and are publically available, 
by searching on https://www.regulations.gov under Docket ID NRC-2012-
0305. You may submit comments by any of the following methods:
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0305. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
     Mail comments to: Cindy Bladey, Chief, Rules, 
Announcements, and Directives Branch (RADB), Office of Administration, 
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
     Fax comments to: RADB at 301-492-3446.
    For additional direction on accessing information and submitting 
comments, see ``Accessing Information and Submitting Comments'' in the 
SUPPLEMENTARY INFORMATION section of this document.

SUPPLEMENTARY INFORMATION:

I. Accessing Information and Submitting Comments

A. Accessing Information

    Please refer to Docket ID NRC-2012-0305 when contacting the NRC 
about the availability of information regarding this document. You may 
access 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-2012-0305.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly-available documents online in the NRC 
Library 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-2012-0305 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 that you do not want to be publicly disclosed in your 
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

[[Page 76079]]

submissions to remove such information before making the comment 
submissions available to the public or entering the comment submissions 
into ADAMS.

Notice of Consideration of Issuance of Amendments to Facility Operating 
Licenses and Combined Licenses, Proposed No Significant Hazards 
Consideration Determination, and Opportunity for a Hearing

    The 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.
    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 ``Rules of 
Practice for Domestic Licensing Proceedings'' 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 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.
    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 E-Filing rule (72 FR 49139; 
August 28, 2007). The E-Filing process requires participants to submit 
and serve all adjudicatory documents over the internet, or in some 
cases to mail copies on electronic storage media. Participants may not 
submit paper copies of their filings unless they seek an exemption in 
accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 10 
days prior to the filing deadline, the participant should contact the 
Office of the Secretary by email at

[[Page 76080]]

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.
    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' 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 agency'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 Web site 
at https://www.nrc.gov/site-help/e-submittals.html, by email at 
MSHD.Resource@nrc.gov, or by a toll-free call at 1-866 672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., 
Eastern Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland, 20852, Attention: Rulemaking and Adjudications Staff. 
Participants filing a document in this manner are responsible for 
serving the document on all other participants. Filing is considered 
complete by first-class mail as of the time of deposit in the mail, or 
by courier, express mail, or expedited delivery service upon depositing 
the document with the provider of the service. A presiding officer, 
having granted an exemption request from using E-Filing, may require a 
participant or party to use E-Filing if the presiding officer 
subsequently determines that the reason for granting the exemption from 
use of E-Filing no longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
https://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the 
Commission, or the presiding officer. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law requires submission of such information. 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 following three 
factors in 10 CFR 2.309(c)(1): (i) The information upon which the 
filing is based was not previously available; (ii) the information upon 
which the filing is based is materially different from information 
previously available; and (iii) the filing has been submitted in a 
timely fashion based on the availability of the subsequent information.
    For further details with respect to this license amendment 
application, see the application for amendment which is available for 
public inspection at the NRC's PDR, located at One White Flint North, 
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 
20852. Publicly available documents created or received at the NRC are 
accessible electronically through ADAMS in the NRC Library at https://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to 
ADAMS or who encounter problems in accessing the documents located in 
ADAMS, should contact the NRC's PDR Reference staff at 1-800-397-4209, 
301-415-4737, or by email to pdr.resource@nrc.gov.

Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, Donald 
C. Cook Nuclear Plant, Units 1 and 2, Berrien County, Michigan

    Date of amendment request: September 12, 2012.

[[Page 76081]]

    Description of amendment request: The proposed amendment would 
revise Technical Specification (TS) 5.5.7, ``Steam Generator (SG) 
Program,'' TS 5.6.7, ``Steam Generator Tube Inspection Report,'' and 
Limiting Condition for Operation (LCO) 3.4.17, ``Steam Generator Tube 
Integrity,'' for Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. The 
changes are consistent with NRC's approved Technical Specifications 
Task Force (TSTF) Traveler TSTF-510, Revision 2, ``Revision to Steam 
Generator Program Inspection Frequencies and Tube Sample Selection'' 
(ADAMS Accession Number ML110610350). The availability of this TS 
improvement was published in the Federal Register on October 27, 2011 
(76 FR 66763), as part of the consolidated line item improvement 
process (CLIIP).
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:
    1. Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed change revises the Steam Generator (SG) Program to 
modify the frequency of verification of SG tube integrity and SG 
tube sample selection. A steam generator tube rupture (SGTR) event 
is one of the design basis accidents that are analyzed as part of a 
plant's licensing basis. The proposed SG tube inspection frequency 
and sample selection criteria will continue to ensure that the SG 
tubes are inspected such that the probability of an SGTR is not 
increased. Section 4.0, Technical Analysis, of the TSTF demonstrates 
that the change in frequencies will not increase the probability of 
an SGTR. The consequences of an SGTR are bounded by the conservative 
assumptions in the design basis accident analysis. The proposed 
change will not cause the consequences of an SGTR to exceed those 
assumptions.
    Therefore, it is concluded that 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 changes to the Steam Generator Program will not 
introduce any adverse changes to the plant design basis or 
postulated accidents resulting from potential tube degradation. The 
proposed change does not affect the design of the SGs or their 
method of operation. In addition, the proposed change does not 
impact any other plant system or component.
    Therefore, it is concluded that this change does not create the 
possibility of a new or different kind of accident from any accident 
previously evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The SG tubes in pressurized water reactors are an integral part 
of the reactor coolant pressure boundary and, as such, are relied 
upon to maintain the primary system's pressure and inventory. As 
part of the reactor coolant pressure boundary, the SG tubes are 
unique in that they are also relied upon as a heat transfer surface 
between the primary and secondary systems such that residual heat 
can be removed from the primary system. In addition, the SG tubes 
also isolate the radioactive fission products in the primary coolant 
from the secondary system. In summary, the safety function of an SG 
is maintained by ensuring the integrity of its tubes.
    Steam generator tube integrity is a function of the design, 
environment, and the physical condition of the tube. The proposed 
change does not affect tube design or operating environment. The 
proposed change will continue to require monitoring of the physical 
condition of the SG tubes such that there will not be a reduction in 
the margin of safety compared to the current requirements.
    Therefore, it is concluded that 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: Robert B. Haemer, Senior Nuclear Counsel, 
One Cook Place, Bridgman, MI 49106.
    NRC Branch Chief: Robert D. Carlson.

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

    Date of amendment request: August 21, 2012, as supplemented on 
November 7, 2012.
    Description of amendment request: The amendment proposes to revise 
the MNGP Renewed Facility Operating License and Technical 
Specifications (TSs) to reflect editorial corrections to the operating 
license, including (1) revision of outdated references to the Nuclear 
Management Company, LLC to state Northern States Power Company (NSPM); 
(2) removal of an outdated reference to a spent fuel pool storage 
capacity letter; (3) administrative corrections, including correction 
of an incorrect phrase in the Core Operating Limits Report (COLR) 
specification; and (4) removal of obsolete information, including 
removal of the Operating Power Range Monitoring (OPRM) System note in 
TS Table 3.3.1.1-1 and removal of analytical methods no longer utilized 
from the COLR specification.
    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 MNGP TS and Updated Safety Analysis Report (USAR) provide 
the specific limitations on the number of fuel assemblies in the 
MNGP spent fuel pool, fresh fuel storage vault, and the reactor 
core. Removing the outdated letter reference from License Condition 
2.B.2 in the Renewed [Facility] Operating License (ROL) has no 
effect on these limitations or on the supporting evaluations.
    The proposed changes to the TS and ROL are administrative or 
editorial in nature and do not impact the physical configuration or 
function of plant structures, systems, or components (SSCs) or the 
manner in which SSCs are operated, maintained, modified, tested, or 
inspected. The proposed changes do not impact the initiators or 
assumptions of analyzed events, nor do they impact mitigation of 
accidents or transient events.
    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 MNGP TS and USAR provide the specific limitations on the 
number of fuel assemblies in the MNGP spent fuel pool, fresh fuel 
storage vault, and the reactor core. Removing the outdated letter 
reference from the license condition in the ROL has no effect on 
these limitations or on the supporting evaluations. This proposed 
change does not introduce a new mode of plant operation and does not 
involve a physical modification to the plant. The change will not 
introduce new accident initiators or impact the assumptions made in 
a safety analysis.
    The proposed changes to the TS and ROL are administrative in 
nature and do not alter plant configuration, require that new plant 
equipment be installed, alter assumptions made about accidents 
previously evaluated, or impact the function of plant SSCs or the 
manner in which SSCs are operated, maintained, modified, tested, or 
inspected.
    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.

[[Page 76082]]

    Margin of safety is related to confidence in the ability of the 
fission product barriers to perform their design functions during 
and following postulated accidents. The MNGP TS and USAR provide the 
specific limitations on the number of fuel assemblies in the spent 
fuel pool, fresh fuel storage vault, and the reactor core. Removing 
the outdated letter reference from the license condition in the ROL 
has no effect on these limitations or on the supporting evaluations. 
Accordingly, no margin of safety is affected.
    The proposed changes are administrative in nature and do not 
involve any physical changes to plant SSCs or the manner in which 
SSCs are operated, maintained, modified, tested, or inspected. The 
proposed changes do not involve a change to any safety limits, 
limiting safety system settings, limiting conditions for operation, 
or design parameters for any SSC. The proposed changes do not impact 
any safety analysis assumptions and do not involve a change in 
initial conditions, system response times, or other parameters 
affecting an accident analysis.
    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: Peter M. Glass, Assistant General Counsel, 
Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN 55401.
    NRC Branch Chief: Robert D. Carlson.

Omaha Public Power District, Docket No. 50-285, Fort Calhoun Station, 
Unit 1, Washington County, Nebraska

    Date of amendment request: April 27, 2012.
    Description of amendment request: The proposed amendment would 
revise (1) Technical Specification (TS) LCO 2.16, ``River Level,'' and 
(2) TS Surveillance Requirement 3.2, ``Equipment and Sampling Tests,'' 
and (3) TS Table 3-5, ``Minimum Frequencies for Equipment Tests.'' In 
addition, the amendment would revise the Fort Calhoun Station 
Radiological Emergency Response Plan declaration procedure as licensed 
in the NRC safety evaluation dated October 3, 2008, for conversion of 
the 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 would revise the river level limiting 
condition for operation (LCO) and surveillance requirement (SR) to 
the Fort Calhoun Station (FCS) Technical Specifications (TS) and the 
emergency plan (EP) emergency action level (EAL) entry condition. 
The proposed TS and EAL changes do not alter the physical design of 
the intake structure or any other plant structure, system or 
component (SSC) at FCS. As such, the change does not increase the 
probability of an accident.
    In addition to the previous method of detecting river level 
(bubblers), radar sounding units that will give a more accurate 
indication of river level are being added for providing river level. 
The river level bubblers currently provide indications for EAL 
classifications, specifically initiating conditions (ICs) HU1 and 
HA1. Using the radar sounding units for river level measurements 
increases the reliability and accuracy of the indications for 
classifying these events. Also, the operators will have river level 
indication available in the control room.
    The proposed TS changes for river level model NUREG-0212, 
Standard Technical Specifications for Combustion Engineering 
Pressurized Water Reactors, Revision 2. The proposed changes to the 
EAL conform to the NRC's regulatory guidance regarding the content 
of emergency plans as identified in NUREG-0654, Criteria for 
Preparation and Evaluation of Radiological Emergency Response Plans 
and Preparedness in Support of Nuclear Power Plants, and Nuclear 
Energy Institute (NEI) 99-01, Methodology for Development of 
Emergency Action Levels, Revision 5, dated February 2008.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed TS and EAL changes do not alter the physical 
design, safety limits, or safety analysis assumptions associated 
with the operation of the plant. Hence, the proposed changes do not 
introduce any new accident initiators, nor do they reduce or 
adversely affect the capabilities of any plant structure or system 
in the performance of their safety function.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed TS LCO requirements ensure there is adequate river 
level present to assure safe reactor operation and are necessary to 
ensure safety systems accomplish their safety function for design 
basis accident events. Adding an additional (SR) to the FCS TS for 
taking river level measurements on a daily frequency will not 
adversely impact any margin of safety. These proposed TS changes for 
the river level requirements model those provided in NUREG-0212, 
Revision 2.
    The proposed EAL changes ensure there is adequate protection 
provided for the health and safety of the public and the employees 
of OPPD [Omaha Public Power District]. These proposed changes will 
result in classification of the ALERT level at an earlier (lower) 
flood level than in the original EAL.
    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: David A. Repka, Esq., Winston & Strawn, 1700 
K Street NW., Washington, DC 20006-3817.
    NRC Branch Chief: Michael T. Markley.

Virginia Electric and Power Company, Docket Nos. 50-280 and 50-281, 
Surry Power Station, Units 1 and 2, Surry County, Virginia

    Date of amendment request: September 26, 2012.
    Description of amendment request: The proposed amendments establish 
the requirements for the use of a temporary supply line (jumper) to 
provide service water to the component cooling heat exchangers.
    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. Involve a significant increase in the probability or 
consequences of an accident previously evaluated.
    The SW [Service Water] and CC [Component Cooling] Water Systems 
will function as designed under the unit operating constraints 
specified by this project (i.e., Unit 2 in operation and Unit 1 in a 
refueling outage), and the potential for a loss of component cooling 
is already addressed by Station Abnormal Procedures. Therefore, 
there is no increase in the probability of an accident previously 
evaluated. The possibility of flooding due to failure of the 
temporary SW supply jumper in the Turbine Building basement has been 
evaluated and dispositioned by the implementation of appropriate 
project constraints and compensatory measures to preclude damage to 
the temporary SW jumper and to respond to a postulated flooding 
event. During the time the temporary SW jumper is in service, the 
installed manual isolation valve in the SW jumper will be under 
administrative control 24 hours/day; the operator assigned to the 
administrative control will be directed

[[Page 76083]]

to close the valve and isolate the SW flow to the CCHXs [component 
cooling heat exchangers] to conserve Intake Canal inventory. In 
addition, a 24 hours/day flood watch will be established when the 
jumper is in service. Therefore, the consequences of an accident 
previously evaluated are not increased.
    2. Create the possibility of a new or different kind of accident 
from any accident previously evaluated.
    The SW and CC Water Systems' design functions and basic 
configurations are not being altered as a result of using the 
temporary SW jumper. The temporary jumper is designed to be safety-
related and seismic with the design attributes of the normal SW 
supply line, except for the automatic isolation function and 
complete missile and heavy load drop protection. The design 
functions of the SW and CC Water Systems are unchanged as a result 
of the proposed changes due to (1) required plant conditions, (2) 
compensatory measures, (3) a contingency action plan for restoration 
of the normal SW supply if required, and (4) strict administrative 
control of the installed manual isolation valve to preclude flooding 
or to isolate non-essential SW within the design basis assumed time 
limits to maintain Intake Canal inventory. Unit 1 will be in a plant 
condition that will provide adequate time to restore the normal SW 
supply, if required. Therefore, since the SW and CC Water Systems 
will basically function as designed and will be operated in their 
basic configuration, the possibility of a new or different type of 
accident than previously evaluated in the UFSAR is not created.
    3. Involve a significant reduction in a margin of safety.
    The margin of safety as defined in the Technical Specifications 
is not significantly reduced since an operable SW flowpath to the 
required number of CCHXs is provided, and unit operating 
constraints, project constraints, compensatory measures, and 
contingency action plan will be implemented as required to ensure 
the integrity and the capability of the SW flowpath. The use of the 
temporary SW jumper will be limited to the time period when missile 
producing weather is not expected, and Unit 1 meets specified unit 
conditions. Therefore, the temporary SW jumper, under the imposed 
project constraints and compensatory measures, provides comparable 
reliability as the normal SW supply line. Furthermore, an evaluation 
using the Probabilistic Risk Assessment model was conducted for the 
use of the temporary SW jumper. The evaluation concluded that the 
increase in annual core damage and large, early release frequencies 
associated with the proposed License amendment Request is 
characterized as ``small changes'' consistent with RG [Regulatory 
Guide] 1.174. In addition, the incremental conditional core damage 
and large, early release probabilities associated with the proposed 
License Amendment Request are within the acceptance criteria in RG 
1.177. Thus, the margin of safety is not significantly reduced.

    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: Lillian M. Cuoco, Esq., Senior Counsel, 
Dominion Resources Services, Inc., 120 Tredegar St., RS-2, Richmond, VA 
23219.
    NRC Branch Chief: Robert Pascarelli.

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 are available for public inspection at 
the Public Document Room (PDR), located at One White Flint North, Room 
O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. 
Publicly available documents created or received at the NRC are 
accessible electronically through the Agencywide Documents Access and 
Management System (ADAMS) in the NRC Library at https://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there 
are problems in accessing the documents located in ADAMS, contact the 
PDR's Reference staff at 1-800-397-4209, 301-415-4737 or by email to 
pdr.resource@nrc.gov.

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

    Date of amendment request: April 12, 2012.
    Description of amendment request: The proposed amendment would 
permanently revise Technical Specification (TS) 6.8.4.g, ``Steam 
Generator (SG) Program,'' to exclude a portion of the steam generator 
tubes below the top of the steam generator tubesheet from periodic 
inspections. Inclusion of the permanent alternate repair criteria 
(PARC) in TS 6.8.4.g permits deletion of the previous temporary 
alternate repair criteria (TARC) for Cycle 15. In addition, this 
amendment request also revises the reporting criteria in TS 6.9.1.7, 
``Steam Generator Tube Inspection Report,'' to remove reference to the 
previous Cycle 15 TARC, and adds reporting requirements specific to the 
PARC.
    Date of issuance: December 6, 2012.
    Effective date: As of the date of issuance, and shall be 
implemented within 30 days.
    Amendment No.: 255.
    Renewed Facility Operating License No. NPF-69: Amendment revised 
the License and Technical Specifications.
    Date of initial notice in Federal Register: May 29, 2012 (77 FR 
31658).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 6, 2012.
    No significant hazards consideration comments received: No.

Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc., 
Docket No. 50-458, River Bend Station, Unit 1, West Feliciana Parish, 
Louisiana

    Date of amendment request: December 8, 2011, as supplemented by 
letters dated July 20 and October 26, 2012.
    Brief description of amendment: The amendment revised Technical 
Specification 3.8.1, ``AC Sources--Operating,'' to include provisions 
for testing of the automatic transfer function from the onsite 22 
kiloVolt bus to offsite power for Division III and the associated 
Standby Service Water Pump powered by the Division III bus.
    Date of issuance: December 5, 2012.
    Effective date: As of the date of issuance and shall be implemented

[[Page 76084]]

prior to startup from the next refueling outage, currently scheduled 
for early 2013.
    Amendment No.: 176.
    Facility Operating License No. NPF-47: The amendment revised the 
Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: May 1, 2012 (77 FR 
25757). The supplemental letters dated July 20 and October 26, 2012, 
provided additional information that clarified the application, did not 
expand the scope of the application as originally noticed, and did not 
change the staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 5, 2012.
    No significant hazards consideration comments received: No.

Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc., 
Docket No. 50-458, River Bend Station, Unit 1, West Feliciana Parish, 
Louisiana

    Date of amendment request: June 20, 2012.
    Brief description of amendment: The amendment revised the scope of 
Cyber Security Plan (CSP) Implementation Schedule Milestone 6 
and paragraph 2.E of the facility operating license. The amendment 
modified the scope of Milestone 6 to apply to the technical 
cyber security controls only. The operational and management controls, 
as described in Nuclear Energy Institute (NEI) 08-09, Revision 6, would 
be implemented concurrent with the full implementation of the cyber 
security program (Milestone 8). Thus, all CSP activities would 
be fully implemented by the completion date, currently identified in 
Milestone 8 of the licensee's CSP implementation schedule.
    Date of issuance: December 5, 2012.
    Effective date: As of the date of issuance and shall be implemented 
by December 31, 2012.
    Amendment No.: 177.
    Facility Operating License No. NPF-47: The amendment revised the 
Facility Operating License.
    Date of initial notice in Federal Register: September 11, 2012 (77 
FR 55867).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 5, 2012.
    No significant hazards consideration comments received: No.

Entergy Nuclear Operations, Inc., Docket No. 50-247, Indian Point 
Nuclear Generating Unit 2, Westchester County, New York

    Date of application for amendment: October 18, 2011, as 
supplemented by letters dated April 27, and October 2, 2012.
    Brief description of amendment: The amendment changes the Technical 
Specification Section 3.3.3, ``Post Accident Monitoring 
Instrumentation,'' Table 3.3.3-1, ``Post Accident Monitoring 
Instrumentation,'' to revise the existing requirement for two channels 
of the Containment Water Level (Containment Sump) function and two 
channels of the Containment Sump Water Level (Recirculation Sump) 
function to only require two Containment Water Level channels. This is 
consistent with the Standard Technical Specification NUREG-1431.
    Date of issuance: November 28, 2012.
    Effective date: As of the date of issuance, and shall be 
implemented within 30 days.
    Amendment No.: 270.
    Facility Operating License No. DPR-26: The amendment revised the 
License and the Technical Specifications.
    Date of initial notice in Federal Register: December 27, 2011 (76 
FR 80975). The supplements dated April 27, and October 2, 2012, 
provided additional information that clarified the application, did not 
expand the scope of the application as originally noticed, and did not 
change the NRC staff's original proposed no significant hazards 
consideration determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated November 28, 2012.
    No significant hazards consideration comments received: No.

Entergy Nuclear Operations, Inc., Docket Nos. 50-003, 50-247, and 50-
286, Indian Point Nuclear Generating Units 1, 2, and 3, (IP1, IP2, and 
IP3) Westchester County, New York

    Date of application for amendment: June 14, 2012. A publicly 
available version is available at ADAMS Accession No. ML12184A050.
    Brief description of amendment: The amendments would revise the 
Cyber Security Plan Implementation Schedule as approved in license 
amendments issued on August 2, 2011 (ADAMS Accession No. ML11152A027).
    Date of issuance: November 28, 2012.
    Effective date: These license amendments are effective as of the 
date of their issuance and shall be implemented by December 31, 2012.
    Amendment Nos.: 56 for IP1, 269 for IP2, and 247 for IP3, 
respectively.
    Facility Operating License Nos. DPR-5, DPR-26, and DPR-64: The 
amendment revised the Licenses.
    Date of initial notice in Federal Register: September 11, 2012 (77 
FR 55869).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated November 28, 2012.
    No significant hazards consideration comments received: No.

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

    Date of application for amendment: June 22, 2010.
    Brief description of amendment: The amendment revised the Cyber 
Security Plan Implementation Schedule as approved in license amendment 
issued on August 19, 2011 (ADAMS Accession No. ML11152A011).
    Date of issuance: December 12, 2012.
    Effective date: This license amendment is effective as of the date 
of its issuance and shall be implemented by December 31, 2012.
    Amendment No.: 303.
    Renewed Facility Operating License No. DPR-59: The amendment 
revised the License
    Date of initial notice in Federal Register: October 9, 2012 (77 FR 
61437).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 12, 2012.
    No significant hazards consideration comments received: Yes. The 
Safety Evaluation dated December 12, 2012, provides the discussion of 
the comments received from the New York State.

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

    Date of application for amendment: June 20, 2012, as supplemented 
by letter dated November 28, 2012.
    Brief description of amendment: The amendment revises the scope of 
the Cyber Security Plan Implementation Schedule Milestone No. 6 and the 
existing license condition in the renewed facility operating license.
    Date of issuance: December 5, 2012.
    Effective date: As of the date of issuance and shall be implemented 
by December 31, 2012.
    Amendment No.: 248.
    Facility Operating License No. DPR-20: Amendment revised the 
Technical Specifications.

[[Page 76085]]

    Date of initial notice in Federal Register: September 11, 2012 (77 
FR 55869). The supplemental letter contained clarifying information and 
did not change the initial no significant hazards determination, and 
did not expand the scope of the original Federal Register Notice.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 5, 2012.
    No significant hazards consideration comments received: No.

Entergy Operations, Inc., Docket No. 50-313, Arkansas Nuclear One, Unit 
1, and Docket No. 50-368, Arkansas Nuclear One, Unit 2, Pope County, 
Arkansas

    Date of amendment request: June 18, 2012.
    Brief description of amendment: The amendments revised the scope of 
the Cyber Security Plan (CSP) Implementation Schedule Milestone 
6 and the physical protection license conditions in the 
facility operating licenses. The amendments modified the scope of 
Milestone 6 to apply to the technical cyber security controls 
only. The operational and management controls, as described in Nuclear 
Energy Institute (NEI) 08-09, Revision 6, would be implemented 
concurrent with the full implementation of the cyber security program 
(Milestone 8). Thus, all CSP activities would be fully 
implemented by the completion date, currently identified in Milestone 
8 of the licensee's CSP implementation schedule.
    Date of issuance: December 5, 2012.
    Effective date: As of the date of issuance and shall be implemented 
by December 31, 2012.
    Amendment Nos.: Unit 1--247; Unit 2--295.
    Renewed Facility Operating License No. DPR-51 (Unit 1) and NPF-6 
(Unit 2): The amendments revised the Facility Operating Licenses.
    Date of initial notice in Federal Register: September 11, 2012 (77 
FR 55871).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 5, 2012.
    No significant hazards consideration comments received: No.

Entergy Operations, Inc., System Energy Resources, Inc., South 
Mississippi Electric Power Association, and Entergy Mississippi, Inc., 
Docket No. 50-416, Grand Gulf Nuclear Station, Unit 1, Claiborne 
County, Mississippi

    Date of application for amendment: June 27, 2012.
    Brief description of amendment: The amendment revised the scope of 
Cyber Security Plan (CSP) Implementation Schedule Milestone 6 
and paragraph 2.E of the facility operating license. The amendment 
modified the scope of Milestone 6 to apply to the technical 
cyber security controls only. The operational and management controls, 
as described in Nuclear Energy Institute (NEI) 08-09, Revision 6, would 
be implemented concurrent with the full implementation of the cyber 
security program (Milestone 8). Thus, all CSP activities would 
be fully implemented by the completion date, currently identified in 
Milestone 8 of the licensee's CSP implementation schedule.
    Date of issuance: December 5, 2012.
    Effective date: As of the date of issuance and shall be implemented 
by December 31, 2012.
    Amendment No: 192.
    Facility Operating License No. NPF-29: The amendment revised the 
Facility Operating License.
    Date of initial notice in Federal Register: September 11, 2012 (77 
FR 55872).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 5, 2012.
    No significant hazards consideration comments received: No.

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

    Date of application for amendments: June 13, 2012.
    Brief description of amendments: The amendment approves a change in 
scope of Cyber Security Plan Implementation Milestone 6, and revise 
License Condition 2.C.(5), ``Physical Protection,'' of the Renewed 
Facility Operating License for the Duane Arnold Energy Center.
    Date of issuance: November 28, 2012.
    Effective date: This license amendment is effective as of the date 
of issuance and shall be implemented by December 31, 2012.
    Amendment No.: 284.
    Renewed Facility Operating License No. DPR-49: Amendment revised 
the Renewed Facility Operating License.
    Date of initial notice in Federal Register: September 11, 2012 (77 
FR 55873).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated November 28, 2012.
    No significant hazards consideration comments received: No.

PSEG Nuclear LLC, Docket Nos. 50-354, 50-272 and 50-311, Hope Creek 
Generating Station and Salem Nuclear Generating Station, Units 1 and 2, 
Salem County, New Jersey

    Date of application for amendments: July 26, 2012.
    Brief description of amendments: The amendments revise the existing 
license condition regarding physical protection in each of the three 
facility operating licenses (FOLs) to approve a change to the scope of 
Implementation Milestone No. 6 of the Cyber Security Plan. Per the FOL 
revisions, Implementation Milestone No. 6 will only apply to the 
technical cyber security controls for the Hope Creek Generating Station 
and the Salem Nuclear Generating Station, Units 1 and 2. The amendments 
were submitted pursuant to 10 CFR 50.90, ``Application for amendment of 
license, construction permit, or early site permit.''
    Date of issuance: December 10, 2012.
    Effective date: The license amendments are effective as of the date 
of issuance.
    Amendment Nos.: Hope Creak--192, Salem Unit 1--302, and Unit 2--
285.
    Facility Operating License Nos. NPF-57, DPR-70 and DPR-75: The 
amendments revised the FOLs.
    Date of initial notice in Federal Register: September 11, 2012 (77 
FR 55875).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated December 10, 2012.
    No significant hazards consideration comments received: No.

Southern Nuclear Operating Company, Inc., Docket Nos. 50-348 and 50-
364, Joseph M. Farley Nuclear Plant (FNP), Units 1 and 2, Houston 
County, Alabama, and Southern Nuclear Operating Company, Inc., Docket 
Nos. 50-424 and 50-425, Vogtle Electric Generating Plant (VEGP), Units 
1 and 2, Burke County, Georgia

    Date of amendment request: January 12, 2012, as supplemented on 
August 15 and September 7, 2012.
    Brief description of amendment request: The amendments revise the 
Technical Specifications (TSs) to extend the reactor coolant pump motor

[[Page 76086]]

flywheel examination frequency from a 10-year interval to an interval 
not to exceed 20 years. The reactor coolant pump flywheel inspection 
program in the TS is also revised to reflect consistency with 
Regulatory Guide 1.14, Revision 1.
    Date of issuance: December 5, 2012.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days.
    Amendment Nos.: FNP Unit 1--190 and Unit 2--185; VEGP Unit 1--168 
and Unit 2--150.
    Facility Operating License Nos. NPF-2 and NPF-8: The amendments 
changed the licenses and the TSs.
    Date of initial notice in Federal Register: February 21, 2012 (77 
FR 10000) for FNP and March 6, 2012 (77 FR 13373) for VEGP.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated December 5, 2012.
    No significant hazards consideration comments received: No.

Tennessee Valley Authority, Docket No. 50-390, Watts Bar Nuclear Plant, 
Unit 1, Rhea County, Tennessee

    Date of application for amendment: March 8, 2012 as supplemented 
July 18, 2012.
    Brief description of amendment: The amendment revised (1) Technical 
Specification (TS) 3.3.7, ``Control Room Emergency Ventilation System 
(CREVS) Actuation Instrumentation,'' by changing the Allowable Value 
for the main control room air intake radiation monitoring 
instrumentation in Table 3.3.7-1 from less than or equal to (<=) 9.45E-
05 micro-Curie per cubic centimeter ([micro]Ci/cc) (3,308 counts per 
minute (cpm)) to <= 1.647E-04 [micro]Ci/cc (3,308 cpm); and (2) TS 
3.4.16, ``RCS Specific Activity,'' by lowering the DOSE EQUIVALENT 
iodine 131 spike limit from 21 micro-Curie/gram ([micro]Ci/gm) to 14 
[micro]Ci/gm in Required Action A.1 and Condition C.
    Date of issuance: December 5, 2012.
    Effective date: As of the date of issuance and shall be implemented 
no later than 60 days from date of issuance.
    Amendment No.: 91.
    Facility Operating License No. NPF-90: Amendment revised the 
License and TSs.
    Date of initial notice in Federal Register: May 15, 2012 (77 FR 
28633). The supplement dated July 18, 2012, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the staff's 
original proposed no significant hazards consideration determination as 
published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 5, 2012.
    No significant hazards consideration comments received: No.

Union Electric Company, Docket No. 50-483, Callaway Plant, Unit 1, 
Callaway County, Missouri

    Date of application for amendment: September 22, 2011, as 
supplemented by letter dated August 6, 2012.
    Brief description of amendment: The amendment revised Required 
Action B.1 of Technical Specification (TS) 3.3.6, ``Containment Purge 
Isolation Instrumentation,'' such that a Note is added to the Required 
Action to conditionally allow containment mini-purge supply and exhaust 
valves that have been closed in accordance with the Action to be opened 
under administrative controls as required for certain operational 
needs. The proposed change is similar to allowances already in place in 
TS 3.6.3, ``Containment Isolation Valves,'' and TS 3.9.4, ``Containment 
Penetrations.''
    Date of issuance: December 7, 2012.
    Effective date: As of its date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 205.
    Facility Operating License No. NPF-30: The amendment revised the 
Operating License and Technical Specifications.
    Date of initial notice in Federal Register: June 26, 2012 (77 FR 
38097). The supplement dated August 6, 2012, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the staff's 
original proposed no significant hazards consideration determination as 
published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 7, 2012.
    No significant hazards consideration comments received: No.

Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek 
Generating Station, Coffey County, Kansas

    Date of amendment request: February 23, 2011, as supplemented by 
letter dated October 25, 2012.
    Brief description of amendment: The amendment revised the Wolf 
Creek Generating Station Technical Specifications (TSs) 3.3.7, 
``Control Room Emergency Ventilation System (CREVS) Actuation 
Instrumentation,'' 3.3.8, ``Emergency Exhaust System (EES) Actuation 
Instrumentation,'' 3.7.10, ``Control Room Emergency Ventilation System 
(CREVS),'' 3.7.11, ``Control Room Air Conditioning System (CRACS),'' 
3.7.13, ``Emergency Exhaust System (EES),'' 3.8.2, ``AC [Alternating 
Current] Sources--Shutdown,'' 3.8.5, ``DC [Direct Current] Sources--
Shutdown,'' 3.8.8, ``Inverters--Shutdown,'' and 3.8.10, ``Distribution 
Systems--Shutdown.'' Specifically, the amendment: (1) Deleted MODES 5 
and 6 from the Limiting Condition for Operation (LCO) Applicability for 
the CREVS and its actuation instrumentation (TS 3.7.10 and TS 3.3.7, 
respectively); (2) deleted the Required Action from TS 3.7.10 and TS 
3.7.11 that requires verifying that the OPERABLE CREVS/CRACS train is 
capable of being powered by an emergency power source; (3) revised TS 
3.7.13 by incorporating a 7-day Completion Time for restoring an 
inoperable EES train to OPERABLE status during shutdown conditions; (4) 
adopted NRC-approved Technical Specification Task Force (TSTF) Change 
Traveler TSTF-36-A, Revision 4, ``Addition of LCO 3.0.3 N/A [not 
applicable] to shutdown electrical power specifications,'' for TSs 
3.3.8, 3.7.13, 3.8.2, 3.8.5, 3.8.8, and 3.8.10; and (5) added a more 
restrictive change to the LCO Applicability for TSs 3.8.2, 3.8.5, 
3.8.8, and 3.8.10 such that these LCOs apply not only during MODES 5 
and 6, but also during the movement of irradiated fuel assemblies 
regardless of the MODE in which the plant is operating.
    Date of issuance: December 5, 2012.
    Effective date: As of its date of issuance and shall be implemented 
within 90 days of the date of issuance.
    Amendment No.: 200.
    Renewed Facility Operating License No. NPF-42. The amendment 
revised the Operating License and Technical Specifications.
    Date of initial notice in Federal Register: August 23, 2011 (76 FR 
52704). The supplemental letter dated October 25, 2012, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination as published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 5, 2012.

[[Page 76087]]

    No significant hazards consideration comments received: No.

Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek 
Generating Station, Coffey County, Kansas

    Date of amendment request: March 29, 2012.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 5.5.9, ``Steam Generator (SG) Program,'' to exclude 
portions of the tube below the top of the steam generator tubesheet 
from periodic steam generator tube inspections. In addition, the 
proposed amendment revises TS 5.6.10, ``Steam Generator Tube Inspection 
Report,'' to remove reference to previous interim alternate repair 
criteria and provide reporting requirements specific to the permanent 
alternate repair criteria.
    Date of issuance: December 11, 2012.
    Effective date: As of the date of its issuance and shall be 
implemented prior to MODE 4 entry during startup from Refueling Outage 
19, which is currently scheduled to commence on February 4, 2013.
    Amendment No.: 201.
    Renewed Facility Operating License No. NPF-42. The amendment 
revised the Operating License and Technical Specifications.
    Date of initial notice in Federal Register: July 3, 2012 (77 FR 
39525).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 11, 2012.
    No significant hazards consideration comments received: No.

Wolf Creek Nuclear Operating Corporation, Docket No. 50-482, Wolf Creek 
Generating Station, Coffey County, Kansas

    Date of amendment request: June 13, 2012.
    Brief description of amendment: The amendment revised the scope of 
Cyber Security Plan (CSP) Implementation Schedule Milestone 6 
and paragraph 2.E of the renewed facility operating license. The 
amendment modified the scope of Milestone 6 to apply to the 
technical cyber security controls only. The operational and management 
controls, as described in Nuclear Energy Institute (NEI) 08-09, 
Revision 6, would be implemented concurrent with the full 
implementation of the cyber security program (Milestone 8). 
Thus, all CSP activities would be fully implemented by the completion 
date, currently identified in Milestone 8 of the licensee's 
CSP implementation schedule.
    Date of issuance: December 12, 2012.
    Effective date: As of the date of its issuance and shall be 
implemented by December 31, 2012.
    Amendment No.: 202.
    Renewed Facility Operating License No. NPF-42. The amendment 
revised the Operating License.
    Date of initial notice in Federal Register: October 2, 2012 (77 FR 
60156).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated December 12, 2012.
    No significant hazards consideration comments received: No.

Notice of Issuance of Amendments to Facility Operating Licenses and 
Combined Licenses and Final Determination of No Significant Hazards 
Consideration and Opportunity for a Hearing (Exigent Public 
Announcement or Emergency Circumstances)

    During the period since publication of the last biweekly notice, 
the Commission has issued the following amendments. The Commission has 
determined for each of these amendments that the application for the 
amendment complies with the standards and requirements of the Atomic 
Energy Act of 1954, as amended (the Act), and the Commission's rules 
and regulations. The Commission has made appropriate findings as 
required by the Act and the Commission's rules and regulations in 10 
CFR Chapter I, which are set forth in the license amendment.
    Because of exigent or emergency circumstances associated with the 
date the amendment was needed, there was not time for the Commission to 
publish, for public comment before issuance, its usual notice of 
consideration of issuance of amendment, proposed no significant hazards 
consideration determination, and opportunity for a hearing.
    For exigent circumstances, the Commission has either issued a 
Federal Register notice providing opportunity for public comment or has 
used local media to provide notice to the public in the area 
surrounding a licensee's facility of the licensee's application and of 
the Commission's proposed determination of no significant hazards 
consideration. The Commission has provided a reasonable opportunity for 
the public to comment, using its best efforts to make available to the 
public means of communication for the public to respond quickly, and in 
the case of telephone comments, the comments have been recorded or 
transcribed as appropriate and the licensee has been informed of the 
public comments.
    In circumstances where failure to act in a timely way would have 
resulted, for example, in derating or shutdown of a nuclear power plant 
or in prevention of either resumption of operation or of increase in 
power output up to the plant's licensed power level, the Commission may 
not have had an opportunity to provide for public comment on its no 
significant hazards consideration determination. In such case, the 
license amendment has been issued without opportunity for comment. If 
there has been some time for public comment but less than 30 days, the 
Commission may provide an opportunity for public comment. If comments 
have been requested, it is so stated. In either event, the State has 
been consulted by telephone whenever possible.
    Under its regulations, the Commission may issue and make an 
amendment immediately effective, notwithstanding the pendency before it 
of a request for a hearing from any person, in advance of the holding 
and completion of any required hearing, where it has determined that no 
significant hazards consideration is involved.
    The Commission has applied the standards of 10 CFR 50.92 and has 
made a final determination that the amendment involves no significant 
hazards consideration. The basis for this determination is contained in 
the documents related to this action. Accordingly, the amendments have 
been issued and made effective as indicated.
    Unless otherwise indicated, the Commission has determined that 
these amendments satisfy the criteria for categorical exclusion in 
accordance with 10 CFR 51.22. Therefore, pursuant to 10 CFR 51.22(b), 
no environmental impact statement or environmental assessment need be 
prepared for these amendments. If the Commission has prepared an 
environmental assessment under the special circumstances provision in 
10 CFR 51.12(b) and has made a determination based on that assessment, 
it is so indicated.
    For further details with respect to the action see (1) the 
application for amendment, (2) the amendment to Facility Operating 
License or Combined License, as applicable, and (3) the Commission's 
related letter, Safety Evaluation and/or Environmental Assessment, as 
indicated. All of these items are available for public inspection at 
the NRC's Public Document Room (PDR), located at One White Flint North, 
Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 
20852.

[[Page 76088]]

Publicly available documents created or received at the NRC are 
accessible electronically through the Agencywide Documents Access and 
Management System (ADAMS) in the NRC Library at https://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS or if there 
are problems in accessing the documents located in ADAMS, contact the 
PDR Reference staff at 1-800-397-4209, 301-415-4737 or by email to 
pdr.resource@nrc.gov.
    The Commission is also offering an opportunity for a hearing with 
respect to the issuance of the amendment. Within 60 days after the date 
of publication of this notice, any person(s) whose interest may be 
affected by this action may file a request for a hearing and a petition 
to intervene with respect to issuance of the amendment to the subject 
facility operating license or combined license. Requests for a hearing 
and a petition for leave to intervene shall be filed in accordance with 
the Commission's ``Rules of Practice for Domestic Licensing 
Proceedings'' in 10 CFR Part 2. Interested person(s) should consult a 
current copy of 10 CFR 2.309, which is available at the NRC's PDR, 
located at One White Flint North, Room O1-F21, 11555 Rockville Pike 
(first floor), Rockville, Maryland 20852, and electronically on the 
Internet at the NRC's Web site, https://www.nrc.gov/reading-rm/doc-collections/cfr/. If there are problems in accessing the document, 
contact the PDR's Reference staff at 1-800-397-4209, 301-415-4737, or 
by email to pdr.resource@nrc.gov. If a request for a hearing or 
petition for leave to intervene is filed by the above date, the 
Commission or a presiding officer designated by the Commission or by 
the Chief Administrative Judge of the Atomic Safety and Licensing Board 
Panel, will rule on the request and/or petition; and the Secretary or 
the Chief Administrative Judge of the Atomic Safety and Licensing Board 
will issue a notice of a hearing or an appropriate order.
    As required by 10 CFR 2.309, a petition for leave to intervene 
shall set forth with particularity the interest of the petitioner in 
the proceeding, and how that interest may be affected by the results of 
the proceeding. The petition should specifically explain the reasons 
why intervention should be permitted with particular reference to the 
following general requirements: (1) The name, address, and telephone 
number of the requestor or petitioner; (2) the nature of the 
requestor's/petitioner's right under the Act to be made a party to the 
proceeding; (3) the nature and extent of the requestor's/petitioner's 
property, financial, or other interest in the proceeding; and (4) the 
possible effect of any decision or order which may be entered in the 
proceeding on the requestor's/petitioner's interest. The petition must 
also identify the specific contentions which the requestor/petitioner 
seeks to have litigated at the proceeding.
    Each contention must consist of a specific statement of the issue 
of law or fact to be raised or controverted. In addition, the 
requestor/petitioner shall provide a brief explanation of the bases for 
the contention and a concise statement of the alleged facts or expert 
opinion which support the contention and on which the petitioner 
intends to rely in proving the contention at the hearing. The 
petitioner must also provide references to those specific sources and 
documents of which the petitioner is aware and on which the petitioner 
intends to rely to establish those facts or expert opinion. The 
petition must include sufficient information to show that a genuine 
dispute exists with the applicant on a material issue of law or fact. 
Contentions shall be limited to matters within the scope of the 
amendment under consideration. The contention must be one which, if 
proven, would entitle the petitioner to relief. A requestor/petitioner 
who fails to satisfy these requirements with respect to at least one 
contention will not be permitted to participate as a party.
    Those permitted to intervene become parties to the proceeding, 
subject to any limitations in the order granting leave to intervene, 
and have the opportunity to participate fully in the conduct of the 
hearing. Since the Commission has made a final determination that the 
amendment involves no significant hazards consideration, if a hearing 
is requested, it will not stay the effectiveness of the amendment. Any 
hearing held would take place while the amendment is in effect.
    All documents filed in the NRC's adjudicatory proceedings, 
including a request for hearing, a petition for leave to intervene, any 
motion or other document filed in the proceeding prior to the 
submission of a request for hearing or petition to intervene, and 
documents filed by interested governmental entities participating under 
10 CFR 2.315(c), must be filed in accordance with the NRC's E-Filing 
rule (72 FR 49139; August 28, 2007). The E-Filing process requires 
participants to submit and serve all adjudicatory documents over the 
internet, or in some cases to mail copies on electronic storage media. 
Participants may not submit paper copies of their filings unless they 
seek an exemption in accordance with the procedures described below.
    To comply with the procedural requirements of E-Filing, at least 10 
days prior to the filing deadline, the participant should contact the 
Office of the Secretary by email at hearing.docket@nrc.gov, or by 
telephone at 301-415-1677, to request (1) a digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign documents and access the E-Submittal 
server for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a request or 
petition for hearing (even in instances in which the participant, or 
its counsel or representative, already holds an NRC-issued digital ID 
certificate). Based upon this information, the Secretary will establish 
an electronic docket for the hearing in this proceeding if the 
Secretary has not already established an electronic docket.
    Information about applying for a digital ID certificate is 
available on the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals/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.
    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 the NRC guidance 
available on the NRC's public

[[Page 76089]]

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 agency'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 Web site 
at https://www.nrc.gov/site-help/e-submittals.html, by email at 
MSHD.Resource@nrc.gov, or by a toll-free call at 1-866-672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., 
Eastern Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland, 20852, Attention: Rulemaking and Adjudications Staff. 
Participants filing a document in this manner are responsible for 
serving the document on all other participants. Filing is considered 
complete by first-class mail as of the time of deposit in the mail, or 
by courier, express mail, or expedited delivery service upon depositing 
the document with the provider of the service. A presiding officer, 
having granted an exemption request from using E-Filing, may require a 
participant or party to use E-Filing if the presiding officer 
subsequently determines that the reason for granting the exemption from 
use of E-Filing no longer exists.
    Documents submitted in adjudicatory proceedings will appear in the 
NRC's electronic hearing docket which is available to the public at 
https://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the 
Commission, or the presiding officer. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law requires submission of such information. 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.

Pacific Gas and Electric Company, Docket Nos. 50-275 and 50-323, Diablo 
Canyon Nuclear Power Plant, Units 1 and 2, San Luis Obispo County, 
California

    Date of application for amendments: December 2, 2012.
    Brief description of amendments: The amendments made a one-time 
change to Technical Specification (TS) 3.7.10, ``Control Room 
Ventilation System (CRVS),'' to modify the completion time for Required 
Action A.1, from 7 days to 13 days. This change will allow completion 
of a modification and required testing to restore the CRVS actuation 
relays and both CRVS trains to OPERABLE status. TS 3.7.10 Condition A 
Required Action A.1 was entered on November 27, 2012, at 20:38 Pacific 
Standard Time (PST), due to the inoperable CRVS actuation relays and 
the associated completion time will expire on December 4, 2012, at 
20:38 PST.
    Date of issuance: December 4, 2012.
    Effective date: As of its date of issuance and shall be implemented 
prior to the expiration of the 7-day completion time, or December 4, 
2012, at 20:38 PST.
    Amendment Nos.: Unit 1--213; Unit 2--215.
    Facility Operating License Nos. DPR-80 and DPR-82: The amendments 
revised the Facility Operating Licenses and Technical Specifications.
    Public comments requested as to proposed no significant hazards 
consideration (NSHC): No.
    The Commission's related evaluation of the amendments, finding of 
emergency circumstances, state consultation, and final NSHC 
determination are contained in a safety evaluation dated December 4, 
2012 (ADAMS Accession No. ML12338A020).
    Attorney for licensee: Jennifer Post, Esq., Pacific Gas and 
Electric Company, P.O. Box 7442, San Francisco, California 94120.
    NRC Branch Chief: Michael T. Markley.

    Dated at Rockville, Maryland, this 14th day of December 2012.

    For the Nuclear Regulatory Commission.

Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2012-30777 Filed 12-21-12; 4:15 pm]
BILLING CODE 7590-01-P