[Federal Register Volume 76, Number 182 (Tuesday, September 20, 2011)]
[Notices]
[Pages 58303-58311]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-23790]


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NUCLEAR REGULATORY COMMISSION

[NRC-2011-0216]


Biweekly Notice; Applications and Amendments to Facility 
Operating 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 
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 August 25, 2011 to September 7, 2011. The 
last biweekly notice was published on September 6, 2011 (76 FR 55125).

ADDRESSES: Please include Docket ID NRC-2011-0216 in the subject line 
of your comments. Comments submitted in writing or in electronic form 
will be posted on the NRC Web site and on the Federal rulemaking Web 
site http://www.regulations.gov. Because your comments will not be 
edited to remove any identifying or contact information, the NRC 
cautions you against including any information in your submission that 
you do not want to be publicly disclosed.
    The NRC requests that any party soliciting or aggregating comments 
received from other persons for submission to the NRC inform those 
persons that the NRC will not edit their comments to remove any 
identifying or contact information, and therefore, they should not 
include any information in their comments that they do not want 
publicly disclosed.
    You may submit comments by any one of the following methods.
     Federal Rulemaking Web Site: Go to http://www.regulations.gov and search for documents filed under Docket ID NRC-
2011-0216. Address questions about NRC dockets to Carol Gallagher 301-
492-3668; e-mail [email protected].
     Mail comments to: 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.
    You can access publicly available documents related to this notice 
using the following methods:
     NRC's Public Document Room (PDR): The public may examine 
and have copied, for a fee, publicly available documents at the NRC's 
PDR, Room O1-

[[Page 58304]]

F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 
20852.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): Publicly available documents created or received at the NRC 
are accessible electronically through ADAMS in the NRC Library at 
http://www.nrc.gov/reading-rm/adams.html. From this page, the public 
can gain entry into ADAMS, which provides text and image files of the 
NRC's public documents. If you do not have access to ADAMS or if there 
are problems in accessing the documents located in ADAMS, contact the 
NRC's PDR reference staff at 1-800-397-4209, 301-415-4737, or by e-mail 
to [email protected].
     Federal Rulemaking Web Site: Public comments and 
supporting materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID: NRC-2011-0216.

Notice of Consideration of Issuance of Amendments to Facility Operating 
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 Title 10 of the Code of Federal 
Regulations (10 CFR) 50.92, 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. 
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. NRC 
regulations are accessible electronically from the NRC Library on the 
NRC Web site at http://www.nrc.gov/reading-rm/doc-collections/cfr/. If 
a request for a hearing or petition for leave to intervene is filed by 
the above date, the Commission or a presiding officer designated by the 
Commission or by the Chief Administrative Judge of the Atomic Safety 
and Licensing Board Panel, will rule on the request and/or petition; 
and the Secretary or the Chief Administrative Judge of the Atomic 
Safety and Licensing Board will issue a notice of a hearing or an 
appropriate order.
    As required by 10 CFR 2.309, a petition for leave to intervene 
shall set forth with particularity the interest of the petitioner in 
the proceeding, and how that interest may be affected by the results of 
the proceeding. The petition should specifically explain the reasons 
why intervention should be permitted with particular reference to the 
following general requirements: (1) The name, address, and telephone 
number of the requestor or petitioner; (2) the nature of the 
requestor's/petitioner's right under the Act to be made a party to the 
proceeding; (3) the nature and extent of the requestor's/petitioner's 
property, financial, or other interest in the proceeding; and (4) the 
possible effect of any decision or order which may be entered in the 
proceeding on the requestor's/petitioner's interest. The petition must 
also identify the specific contentions which the requestor/petitioner 
seeks to have litigated at the proceeding.
    Each contention must consist of a specific statement of the issue 
of law or fact to be raised or controverted. In addition, the 
requestor/petitioner shall provide a brief explanation of the bases for 
the contention and a concise statement of the alleged facts or expert 
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing. 
The requestor/petitioner must also provide references to those specific 
sources and documents of which the petitioner is aware and on which the 
requestor/petitioner intends to rely to establish those facts or expert 
opinion. The petition must include sufficient information to show that 
a genuine dispute exists with the applicant on a material issue of law 
or fact. Contentions shall be limited to matters within the scope of 
the amendment under consideration. The contention must be one which, if 
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at 
least one contention will not be permitted to participate as a party.
    Those permitted to intervene become parties to the proceeding, 
subject to any limitations in the order granting leave to intervene, 
and have the opportunity to participate fully in the conduct of the 
hearing.
    If a hearing is requested, the Commission will make a final 
determination on the issue of no significant hazards consideration. The 
final determination will serve to decide when the hearing is held. If 
the final determination is that the amendment request involves no 
significant hazards consideration, the Commission may issue the 
amendment and make it immediately effective, notwithstanding the 
request for a hearing. Any hearing held would take place after issuance 
of the amendment. If the final determination is that the amendment 
request involves a significant hazards consideration, then any hearing 
held would take place before the issuance of any amendment.
    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

[[Page 58305]]

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 e-mail at [email protected], or by 
telephone at 301-415-1677, to request (1) A digital identification (ID) 
certificate, which allows the participant (or its counsel or 
representative) to digitally sign documents and access the E-Submittal 
server for any proceeding in which it is participating; and (2) advise 
the Secretary that the participant will be submitting a request or 
petition for hearing (even in instances in which the participant, or 
its counsel or representative, already holds an NRC-issued digital ID 
certificate). Based upon this information, the Secretary will establish 
an electronic docket for the hearing in this proceeding if the 
Secretary has not already established an electronic docket.
    Information about applying for a digital ID certificate is 
available on NRC's public Web site at http://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing 
the E-Submittal server are detailed in NRC's ``Guidance for Electronic 
Submission,'' which is available on the agency's public Web site at 
http://www.nrc.gov/site-help/e-submittals.html. Participants may 
attempt to use other software not listed on the Web site, but should 
note that the NRC's E-Filing system does not support unlisted software, 
and the NRC Meta System Help Desk will not be able to offer assistance 
in using unlisted software.
    If a participant is electronically submitting a document to the NRC 
in accordance with the E-Filing rule, the participant must file the 
document using the NRC's online, Web-based submission form. In order to 
serve documents through the Electronic Information Exchange System, 
users will be required to install a Web browser plug-in from the NRC 
Web site. Further information on the Web-based submission form, 
including the installation of the Web browser plug-in, is available on 
the NRC's public Web site at http://www.nrc.gov/site-help/e-submittals.html.
    Once a participant has obtained a digital ID certificate and a 
docket has been created, the participant can then submit a request for 
hearing or petition for leave to intervene. Submissions should be in 
Portable Document Format (PDF) in accordance with NRC guidance 
available on the NRC public Web site at http://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the 
documents are submitted through the NRC's E-Filing system. To be 
timely, an electronic filing must be submitted to the E-Filing system 
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of 
a transmission, the E-Filing system time-stamps the document and sends 
the submitter an e-mail notice confirming receipt of the document. The 
E-Filing system also distributes an e-mail 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 Web site 
at http://www.nrc.gov/site-help/e-submittals.html, by e-mail at 
[email protected], or by a toll-free call at 1-866-672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., 
Eastern Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 
20852, Attention: Rulemaking and Adjudications Staff. Participants 
filing a document in this manner are responsible for serving the 
document on all other participants. Filing is considered complete by 
first-class mail as of the time of deposit in the mail, or by courier, 
express mail, or expedited delivery service upon depositing the 
document with the provider of the service. A presiding officer, having 
granted an exemption request from using E-Filing, may require a 
participant or party to use E-Filing if the presiding officer 
subsequently determines that the reason for granting the exemption from 
use of E-Filing no longer exists.
    Documents submitted in adjudicatory proceedings will appear in 
NRC's electronic hearing docket which is available to the public at 
http://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the 
Commission, or the presiding officer. Participants are requested not to 
include personal privacy information, such as social security numbers, 
home addresses, or home phone numbers in their filings, unless an NRC 
regulation or other law requires submission of such information. 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. Non-timely filings 
will not be entertained absent a determination by the presiding officer 
that the petition or request should be granted or the contentions 
should be admitted, based on a balancing of the factors specified in 10 
CFR 2.309(c)(1)(i)-(viii).
    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 http://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 PDR Reference staff at 1-800-397-4209, 
301-

[[Page 58306]]

415-4737, or by e-mail to [email protected].

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

    Date of amendment request: May 20, 2011.
    Description of amendment request: The proposed amendment would 
modify the Davis-Besse Nuclear Power Station, Unit No. 1 (DBNPS) 
Technical Specifications (TS) 5.5.8, ``Steam Generator (SG) Program,'' 
to modify the special visual inspection frequency requirements. 
Specifically, TS 5.5.8.g requires visual inspection of the secured 
internal auxiliary feedwater header, header to shroud attached welds, 
and external header thermal sleeves. The proposed amendment would 
replace the time-based frequency requirement with a condition-based 
inspection requirement.
    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.
    This amendment request modifies the frequency requirements for 
performing visual inspections of the secured internal auxiliary 
feedwater (AFWH), the header to shroud attachments welds, and the 
external header thermal sleeves. Previous AFWH repairs adhered to 
applicable code requirements, and steam generator modifications to 
install an external AFWH were implemented using an approved design 
change process. The steam generator's safety-related and seismic 
design requirements did not change. The auxiliary feedwater system's 
safety-related, seismic and accident mitigation requirements did not 
change.
    Historically acceptable TS 5.5.8.g visual inspection results for 
both steam generators indicate no degradation of the internal AFWH 
and its attachment welds, or of the external header thermal sleeves. 
Historically acceptable TS 5.5.8.d.5 eddy current inspections 
indicate no degradation of the steam generator peripheral tubes due 
to the internal AFWH. The acceptable eddy current inspections were 
last completed on both steam generators during the 2010 refueling 
outage, and will continue to be performed until the steam generators 
are replaced. For steam generator 1-B, the last TS 5.5.8.g special 
visual inspection was completed during the 2010 refueling outage, 
and no other required TS 5.5.8.g special visual inspections remain 
before the steam generator's scheduled replacement in 2014. For 
steam generator 2-A, the last TS 5.5.8.g special visual inspection 
was performed during the 1998 refueling outage, and only one TS 
5.5.8.g special visual inspection remains before the end of the 
current inservice inspection interval (September 20, 2012).
    The visual inspection trend indicates that degradation of the 
secured internal AFWH and its attachment welds is not expected to be 
identified, should the required TS 5.5.8.g inspection of the steam 
generator 2-A be performed in 2012, and that is degradation is not 
expected to occur during the remaining planned service life of both 
steam generators before their scheduled replacements in 2014.
    The eddy current inspection trend indicates that the steam 
generator tubes, a part of the reactor coolant system, remain 
unaffected by the internal AFWHs. Significant changes in the gap 
between the steam generator peripheral tubes and the secured AFWHs 
is not expected to be indentified when the next TS 5.5.8.d.5 eddy 
current inspections of steam generators 1-B and 2-A are performed in 
2012, and that significant gap degradation is not expected to occur 
during the remaining planned service life of both steam generators 
before their scheduled replacements in 2014.
    Should significant damage to a steam generator peripheral tube 
occur due to direct contact with the internal AFWH, the postulated 
occurrence would be bounded by the existing Updated Safety Analysis 
Report (USAR) Chapter 15, Section 15.4.2, for the steam generator 
tube rupture accident analysis.
    Modifying the TS 5.5.8.g inspection frequency requirement will 
not significantly increase the probability of an accident previously 
evaluated because historically acceptable inspection results and 
trend indicate that degradation of the secured internal AFWHs is not 
expected to occur during the remaining service life of both steam 
generators.
    Modifying the TS 5.5.8.g inspection frequency requirement will 
cause a change to any dose analyses associated with the USAR Chapter 
15 accidents because accident mitigation functions and requirements 
remain unchanged.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequence of an accident previously 
evaluated.
    2. Does the proposed amendment create the possibility of new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    This amendment request modifies the frequency requirements for 
performing visual inspections of the secured internal AFWH, the 
header to shroud attachment welds, and the external header thermal 
sleeves. This request does not change the design function of the 
reactor coolant system, the steam generators, the AFWS, or the way 
the systems and plant are operated and maintained.
    Therefore, the proposed change does not create the possibility 
of new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    This amendment request modifies the frequency requirements for 
performing visual inspections of the secured internal AFWH, the 
header to shroud attachment welds, and the external header thermal 
sleeves. Historically acceptable TS 5.5.8.g visual inspection 
results for both steam generators indicate no degradation of the 
internal AFWH and its attachment welds, or of the external header 
thermal sleeves. Historically acceptable TS 5.5.8.d.5 eddy current 
inspections indicate no degradation of the steam generator [special 
interest group] peripheral tubes due to the internal AFWH.
    The visual and eddy current inspection trends indicate that 
degradation of the AFWH, or significant changes in the gap between 
the steam generator peripheral tubes and the secured AFWHs, is not 
expected to occur during the remaining service life of both steam 
generators.
    The request does not involve or affect the fuel cladding or the 
containment. The steam generators tubes, a part of the reactor 
coolant system, remain unaffected based on the historically 
acceptable 5.5.8.d.5 eddy current inspection results and trend. This 
request does not involve a physical change to the plant, methods, of 
plant operation, or maintenance of equipment important to safety.
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.
    Based on the above, FENOC concludes that the proposed amendment 
does not involve a significant consideration under the standards set 
forth in 10 CFR 50.92(c), and, accordingly, finding of ``no 
significant hazards consideration'' is justified.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: David W. Jenkins, Attorney, FirstEnergy 
Corporation, Mail Stop A-GO-15, 76 South Main Street, Akron, OH 44308.
    NRC Branch Chief: Jacob I. Zimmerman.

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

    Date of amendment request: August 10, 2011.
    Description of amendment request: The proposed amendment request 
would revise Technical Specification (TS) 3.8.1 ``AC [Alternating 
Current] Sources--Operating.'' It would modify Surveillance Requirement 
(SR) Notes associated with SR 3.8.1, SR 3.8.1.9, SR 3.8.1.10, SR 
3.8.1.11, SR 3.8.1.13, SR 3.8.1.16, SR 3.8.1.18, and SR 3.8.1.19. The 
proposed amendment request would change the Unit 1 TS 3.8.1 to

[[Page 58307]]

permit performance of the Unit 2 integrated safeguards test without 
requiring Unit 1 to be shut down.
    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 do not require physical changes to plant 
systems, structures, or components. The DGs [diesel generators] and 
their associated emergency loads are accident mitigating features. 
As such, testing of the DGs is not associated with a potential 
accident-initiating mechanism. Therefore, the changes do not affect 
accident or transient initiation or consequences.
    The probability or consequences of previously evaluated 
accidents will not be significantly affected by the revised 
Surveillance Notes, because a sufficient number of onsite AC power 
sources will continue to remain available to perform the accident 
mitigation functions associated with the DGs, as assumed in the 
accident analyses.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed changes would not require any new or different 
accidents to be postulated, since no changes are being made to the 
plant that would introduce any new accident causal mechanisms. This 
license amendment request does not impact any plant systems that are 
potential accident initiators; nor does it have any significantly 
adverse impact on any accident mitigating systems.
    Therefore, the proposed changes do 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 alter the permanent plant design, 
including instrument set points, nor does it change the assumptions 
contained in the safety analyses. The DG alternate AC system and 
other required safety systems are designed with sufficient 
redundancy such that a DG from the non-operating unit may have 
surveillance and testing performed while the affected unit is 
operating. The proposed changes do not impact the redundancy or 
availability requirements of offsite power supplies or change the 
ability of the plant to cope with station blackout events.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: General Counsel, Tennessee Valley Authority, 
400 West Summit Hill Drive, ET 11A, Knoxville, Tennessee 37902.
    NRC Branch Chief: Stephen J. Campbell.

Notice of Issuance of Amendments to Facility Operating 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.
    Notice of Consideration of Issuance of Amendment to Facility 
Operating License, 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 NRC's 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 ADAMS in the NRC Library at http://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 
e-mail to [email protected].

Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-
529, and STN 50-530, Palo Verde Nuclear Generating Station, Unit 1, 2, 
and 3, Maricopa County, Arizona

    Date of application for amendment: August 27, 2010, as supplemented 
by letters dated February 11 and May 25, 2011.
    Brief description of amendment: The amendments revised the 
feedwater line break with loss of offsite power and single failure 
(FWLB/LOP/SF) event analysis reported in Chapter 15, Section 15.2.8 of 
the Palo Verde Nuclear Generating Station Updated Final Safety Analysis 
Report. The revisions to the FWLB/LOP/SF analysis reduced (1) The time 
assumed for the commencement of operator action from 30 minutes to 20 
minutes, and (2) the rate of reactor coolant pump bleed-off to the 
reactor drain tank from 3 gallons per minute to zero.
    Date of issuance: August 31, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: Unit 1-187; Unit 2-187; Unit 3-187.
    Facility Operating License Nos. NPF-41, NPF-51, and NPF-74: The 
amendment revised the Operating Licenses.
    Date of initial notice in Federal Register: October 19, 2010 (75 FR 
64361), and June 28, 2011 (76 FR 37853). The supplemental letters dated 
February 11 and May 25, 2011, provided additional information that 
clarified the application, did not expand the scope of the application 
as originally noticed, and did not change the staff's original proposed 
no significant hazards consideration determination as published in the 
Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated August 31, 2011.
    No significant hazards consideration comments received: No.

Carolina Power & Light Company, Docket Nos. 50-325 and 50-324, 
Brunswick Steam Electric Plant, Units 1 and 2, Brunswick County, North 
Carolina

    Date of application for amendments: September 23, 2010.

[[Page 58308]]

    Brief description of amendments: The license amendments revised 
Brunswick Steam and Electric Plant (BSEP), Units 1 and 2 Technical 
Specification (TS) 5.3.1, ``Facility Staff Qualifications.'' The 
amendments added an exception to ANSI N18.1, ``Selection and Training 
of Nuclear Power Plant Personnel,'' for the operations manager (OM) 
qualification. The amendments changed the TS requirement specific to 
the OM holding a senior reactor operator (SRO) license. The revised 
BSEP, Units 1 and 2 TS 5.3.1 refer to TS 5.2.2.f, that states ``The 
operations manager or assistant operations manager shall hold an SRO 
license.'' All other requirements for the OM, specified in ANSI N18.1-
1971, such as a minimum of 8 years of responsible power plant 
experience, would be retained.
    Date of issuance: August 25, 2011.
    Effective date: Date of issuance, shall be implemented within 60 
days of the effective date.
    Amendment Nos.: Unit 1-259 and Unit 2-287.
    Facility Operating License Nos. DPR-71 and DPR-62: Amendments 
revised the technical specifications.
    Date of initial notice in Federal Register: February 8, 2011 (76 FR 
6833).
    The Commission's related evaluation of the amendments is contained 
in a safety evaluation dated August 25, 2011.
    No significant hazards consideration comments received: No.

Detroit Edison Company, Docket No. 50-341, Fermi 2, Monroe County, 
Michigan

    Date of application for amendment: April 8, 2011.
    Brief description of amendment: The amendment revises Fermi 2 
Technical Specification (TS) to define a new time limit for restoring 
inoperable Reactor Coolant System (RCS) leakage detection 
instrumentation to operable status; establish alternate methods of 
monitoring RCS leakage when one or more required monitors are 
inoperable; and make TS Bases changes which reflect the proposed 
changes and more accurately reflect the contents of the facility design 
basis related to operability of the RCS leakage detection 
instrumentation. The request is submitted consistent with the guidance 
contained in NRC-approved Technical Specifications Task Force traveler 
514 (TSTF-514). This technical specification improvement was made 
available by the NRC on December 17, 2010 (75 FR 79048), as part of the 
consolidated line item improvement process.
    Date of issuance: August 26, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 186.
    Facility Operating License No. NPF-43: Amendment revised the 
Technical Specifications and License.
    Date of initial notice in Federal Register: May 31, 2011 (76 FR 
31372).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated August 26, 2011.
    No significant hazards consideration comments received: No.

Duke Energy Carolinas, LLC, et al., Docket Nos. 50-413 and 50-414, 
Catawba Nuclear Station, Units 1 and 2 (Catawba 1 and 2), York County, 
South Carolina

Duke Energy Carolinas, LLC, Docket Nos. 50-369 and 50-370, McGuire 
Nuclear Station, Units 1 and 2 (McGuire 1 and 2), Mecklenburg County, 
North Carolina

Duke Energy Carolinas, LLC, Docket Nos. 50-269, 50-270, and 50-287, 
Oconee Nuclear Station, Units 1, 2, and 3 (Oconee 1, 2, and 3), Oconee 
County, South Carolina

    Date of application for amendments: August 16, 2010, as 
supplemented by letters dated September 27, 2010, March 7, 2011, April 
15, 2011, and August 9, 2011.
    Brief description of amendments: The amendments approved the Cyber 
Security Plan (CSP) and associated implementation schedule, and revised 
the licenses of Renewed Facility Operating License Nos. NPF-35 and NPF-
52 for Catawba 1 and 2, Renewed Facility Operating License Nos. NPF-9 
and NPF-17 for McGuire 1 and 2, and Renewed Facility Operating License 
Nos. DPR-38, DPR-47, and DPR-55, for Oconee 1, 2, and 3, respectively, 
to provide a license condition to require the licensee to fully 
implement and maintain in effect all provisions of the NRC-approved 
CSP. The proposed change is consistent with Nuclear Energy Institute 
(NEI) 08-09, Revision 6, ``Cyber Security Plan for Nuclear Power 
Reactors.''
    Date of issuance: August 31, 2011.
    Effective date: The license amendments are effective as of the date 
of their issuance. The implementation of the CSP, including the key 
intermediate milestone dates and the full implementation date, shall be 
in accordance with the implementation schedule submitted by the 
licensee on August 16, 2010, as supplemented by letters dated September 
27, 2010, March 7, 2011, April 15, 2011, and August 9, 2011, and 
approved by the NRC staff with these license amendments. All subsequent 
changes to the NRC-approved CSP implementation schedule will require 
prior NRC approval pursuant to 10 CFR 50.90.
    Amendment Nos.: 266/262 (Catawba); 264/244 (McGuire); 378/380/379 
(Oconee).
    Renewed Facility Operating License Nos. NPF-35, NPF-52, NPF-9, NPF-
17, DPR-38, DPR-47, and DPR-55: Amendments revised the licenses.
    Date of initial notice in Federal Register: July 7, 2011 (76 FR 
39913). The supplements dated September 27, 2010, March 7, 2011, April 
15, 2011, and August 9, 2011, provided additional information that 
clarified the application, did not expand the scope of the application 
as originally noticed, and did not change the staff's original proposed 
no significant hazards consideration determination.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated August 31, 2011.
    No significant hazards consideration comments received: No.

Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, 
Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon, 
Vermont

    Date of amendment request: November 8, 2010.
    Description of amendment request: The amendment would revise 
Technical Specifications (TS) to eliminate provisions allowing the 
high-pressure coolant injection (HPCI) system and the reactor core 
isolation cooling (RCIC) system to be aligned to the suppression pool 
when required instrument channels are inoperable. In this 
configuration, the HPCI and RCIC systems would not be capable of 
mitigating some plant events. Also, an administrative change to the TS 
Table of Contents is proposed.
    Date of Issuance: August 25, 2011.
    Effective date: As of the date of issuance, and shall be 
implemented within 60 days.
    Amendment No.: 248.
    Facility Operating License No. DPR-28: Amendment revised the 
License and Technical Specifications.
    Date of initial notice in Federal Register: January 11, 2011 (76 FR 
1647).
    The Commission's related evaluation of this amendment is contained 
in a Safety Evaluation dated August 25, 2011.
    No significant hazards consideration comments received: No.

[[Page 58309]]

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

    Date of amendment request: July 16, 2010, as supplemented by 
letters dated September 20, 2010, November 29, 2010, February 15, 2011, 
and April 8, 2011.
    Brief description of amendment request: This amendment was 
submitted in accordance with the provisions of Title 10 of the Code of 
Federal Regulations (10 CFR), 50.4 and 50.90, and requested NRC 
approval of the PNPP CSP, the associated Implementation Schedule, and 
the addition of a sentence to the existing Physical Protection license 
condition in PNPP's Facility Operating License (FOL) to require FENOC 
to fully implement and maintain in effect all provisions of the NRC-
approved CSP.
    Date of issuance: August 29, 2011.
    Effective date: This license amendment is effective as of the date 
of its issuance. The implementation of the CSP, including the key 
intermediate milestone dates and the full implementation date, shall be 
in accordance with the implementation schedule submitted by the 
licensee on April 8, 2011, and approved by the NRC staff with this 
license amendment. All subsequent changes to the NRC-approved CSP 
implementation schedule will require prior NRC approval pursuant to 10 
CFR 50.90.
    Amendment No.: 158.
    Facility Operating License No. NPF-58: The amendment revised PNPP's 
FOL.
    Date of initial notice in Federal Register: November 9, 2010 (75 FR 
68834). The supplemental letters dated September 29, 2010, November 29, 
2010, February 15, 2011, and April 8, 2011, provided additional 
information that clarified the application, did not expand the scope of 
the application as originally noticed, and did not change the Nuclear 
Regulatory Commission staff's original proposed finding of no 
significant hazards consideration determination published in the 
Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated August 29, 2011.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: July 16, 2010, as supplemented by 
letters dated September 28, 2010, November 23, 2010, February 1, 2011, 
and April 8, 2011.
    Brief description of amendment request: This amendment was 
submitted in accordance with the provisions of 10 CFR 50.4 and 10 CFR 
50.90 and requests NRC approval of the DBNPS CSP, the associated 
Implementation Schedule, and the addition of a sentence to the existing 
Physical Protection license condition in DBNP's Facility Operating 
License (FOL) to require FENOC to fully implement and maintain in 
effect all provisions of the NRC-approved DBNPS CSP.
    Date of issuance: August 31, 2011.
    Effective date: This license amendment is effective as of the date 
of its issuance. The implementation of the CSP, including the key 
intermediate milestone dates and the full implementation date, shall be 
in accordance with the implementation schedule submitted by the 
licensee on April 8, 2011, and approved by the NRC staff with this 
license amendment. All subsequent changes to the NRC-approved CSP 
implementation schedule will require prior NRC approval pursuant to 10 
CFR 50.90.
    Amendment No.: 283.
    Facility Operating License No. NPF-3: The amendment revised DBNPS's 
FOL.
    Date of initial notice in Federal Register: February 1, 2011 (76 FR 
5621) The supplemental letters dated September 28, 2010, November 23, 
2010, February 1, 2011, and April 8, 2011, 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 finding of no significant hazards 
consideration determination published in the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated August 31, 2011.
    No significant hazards consideration comments received: No.

Florida Power and Light Company, et al., Docket Nos. 50-335 and 50-389, 
St. Lucie Plant, Unit 1 and 2, St. Lucie County, Florida

    Date of application for amendments: August 2, 2010, as supplemented 
by letters dated September 27 and November 17, 2010, and April 8 and 
June 22, 2011.
    Brief description of amendments: Amendments modify paragraph 3.F, 
``Physical Protection,'' of the licenses of both units. The changes 
incorporate a requirement to fully implement and maintain in effect all 
provisions of the Commission-approved CSP.
    Date of Issuance: August 31, 2011.
    Effective Date: These license amendments are effective as of the 
date of their issuance. The implementation of the CSP, including the 
key intermediate milestone dates and the full implementation date, 
shall be in accordance with the implementation schedule submitted by 
the licensee on April 8, 2011, and approved by the NRC staff with these 
license amendments. All subsequent changes to the NRC-approved CSP 
implementation schedule will require prior NRC approval pursuant to 10 
CFR 50.90.
    Amendment Nos.: Unit 1-211 and Unit 2-160.
    Renewed Facility Operating License Nos. DPR-67 and NPF-16: 
Amendments revised the license.
    Date of initial notice in Federal Register: October 12, 2010 (75 FR 
62600). The supplements dated September 27 and November 17, 2010, and 
April 8 and June 22, 2011, provided additional information that 
clarified the application, did not expand the scope of the application 
as originally noticed, and did not change the staff's original proposed 
no significant hazards consideration determination as published in the 
Federal Register.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated August 31, 2011.
    No significant hazards consideration comments received: No.

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

    Date of application for amendment: December 16, 2010.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 4.2.1, adding Optimized ZIRLO\TM\ fuel rods to the 
fuel matrix in addition to Zircaloy or ZIRLO\TM\ fuel rods that are 
currently in use. The amendment also add a Westinghouse topical report 
regarding Optimized ZIRLO\TM\ as Reference 8 in TS 5.6.5.b, which lists 
the analytical methods used to determine the core operating limits.
    Date of issuance: August 25, 2011.
    Effective date: As of the date of issuance and shall be implemented

[[Page 58310]]

within 60 days from the date of issuance.
    Amendment No.: 316.
    Facility Operating License No. DPR-58: Amendment revised the 
Renewed Operating License and Technical Specifications.
    Date of initial notice in Federal Register: February 22, 2011 (76 
FR 9826).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated August 25, 2011.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: July 13, 2010, as supplemented by 
letters dated February 4 and August 19, 2011.
    Brief description of amendment: The amendment revised language in 
Technical Specification (TS) 2.10.2, ``Reactivity Control Systems and 
Core Physics Parameters Limits,'' and revised table items related to TS 
2.15, ``Instrumentation and Control Systems,'' which pertain to 
operability of the primary and secondary control element assembly (CEA) 
position indication system (CEAPIS) channels. A new surveillance 
requirement was added to TS 3.1, ``Instrumentation and Control,'' to 
verify the position of the CEAs each shift. The surveillance 
requirement for TS 3.1, Table 3-3, Item 1.a was modified to specify 
performance of a CHANNEL CHECK of the primary CEAPIS. By letter dated 
August 19, 2011, the licensee withdrew its proposed changes to Item 2.a 
of TS 3.1, Table 3-3 regarding the secondary CEAPIS.
    Date of issuance: August 31, 2011.
    Effective date: This license amendment is effective as of the date 
of its issuance and shall be implemented within 180 days from the date 
of issuance.
    Amendment No.: 267.
    Renewed Facility Operating License No. DPR-40: The amendment 
revised the operating license and Technical Specifications.
    Date of initial notice in Federal Register: January 25, 2011 (76 FR 
4387). The supplemental letters dated February 4 and August 19, 2011 
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 August 31, 2011.
    No significant hazards consideration comments received: No.

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

    Date of application for amendments: October 4, 2010, as 
supplemented by letters dated April 7, 2011, and May 23, 2011.
    Brief description of amendments: The amendments modify the 
Technical Specification (TS) requirements for snubbers due to revisions 
to the inservice inspection program.
    Date of issuance: August 25, 2011.
    Effective date: As of the date of issuance, to be implemented 
within 60 days.
    Amendment Nos.: 301 and 284.
    Facility Operating License Nos.DPR-70 and DPR-75: The amendments 
revised the TSs and the Facility Operating Licenses.
    Date of initial notice in Federal Register: December 28, 2010 (75 
FR 81672). The letters dated April 7, 2011, and May 23, 2011, provided 
clarifying information that did not change the initial proposed no 
significant hazards consideration determination or expand the 
application beyond the scope of the original Federal Register notice.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated August 25, 2011.
    No significant hazards consideration comments received: No.

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

    Date of application for amendment: November 23, 2009, as 
supplemented December 18, 2009, July 23, 2010, October 1, 2010, April 
7, 2011, June 10, 2011, and July 15, 2011.
    Brief description of amendment: The amendment revised the Facility 
Operating License condition 2.E to add the CSP.
    Date of issuance: August 30, 2011.
    Effective date: As of the date of issuance, the implementation of 
the CSP, including the key intermediate milestone dates and the full 
implementation date, shall be in accordance with the implementation 
schedule submitted by the licensee on November 23, 2009, as 
supplemented by letters dated December 18, 2009, July 23, 2010, October 
1, 2010, April 7, 2011, June 10, 2011, and July 15, 2011, and approved 
by the NRC staff with this license amendment. All subsequent changes to 
the NRC-approved CSP implementation schedule will require prior NRC 
approval pursuant to 10 CFR 50.90.
    Amendment No.: 87.
    Facility Operating License No. NPF-90: Amendment revised the 
License.
    Date of initial notice in Federal Register: August 20, 2010 (75 FR 
51495). TVA's supplements dated October 1, 2010, April 7, 2011, June 
10, 2011, and July 15, 2011, provided additional information that 
clarified the application, did not expand the scope of the application 
as originally noticed proposed and did not change the staff's original 
proposed no significant hazards determination as published in the 
Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated August 30, 2011.
    No significant hazards consideration comments received: No.

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

    Date of application for amendment: October 30, 2009, as 
supplemented May 24, 2011.
    Brief description of amendment: The amendment revised License 
Condition 2.F regarding fire protection of the Operating License NPF-
90.
    Date of issuance: September 1, 2011.
    Effective date: As of the date of issuance and shall be implemented 
no later than 30 days from date of issuance.
    Amendment No.: 88.
    Facility Operating License No. NPF-90: Amendment revised the 
License.
    Date of initial notice in Federal Register: December 15, 2009 (74 
FR 66385). TVA's supplement dated May 24, 2011, 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 determination as published in 
the Federal Register.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated September 1, 2011.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 8th day of September 2011.


[[Page 58311]]


    For the Nuclear Regulatory Commission .
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2011-23790 Filed 9-19-11; 8:45 am]
BILLING CODE 7590-01-P