Biweekly Notice; Applications and Amendments to Facility Operating Licenses; Involving No Significant Hazards Considerations, 64388-64399 [2011-26893]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 76, Number 201 (Tuesday, October 18, 2011)]
[Notices]
[Pages 64388-64399]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-26893]


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

NUCLEAR REGULATORY COMMISSION

[NRC-2011-0241]


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 September 22, 2011 to October 5, 2011. The 
last biweekly notice was published on October 4, 2011(76 FR 61391).
    Addresses: Please include Docket ID NRC-2011-0241 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 https://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 https://www.regulations.gov and search for documents filed under Docket ID NRC-
2011-0241. Address questions about NRC dockets to Carol Gallagher 301-
492-3668; e-mail Carol.Gallagher@nrc.gov.
     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, O1-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 
https://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 pdr.resource@nrc.gov.
     Federal Rulemaking Web Site: Public comments and 
supporting materials related to this notice can be found at https://www.regulations.gov by searching on Docket ID: NRC-2011-0241.

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), Section 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.

[[Page 64389]]

    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 Commission's PDR, located at One White Flint North, Public File 
Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland. 
NRC regulations are accessible electronically from the NRC Library on 
the NRC 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, 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 
ten (10) days prior to the filing deadline, the participant should 
contact the Office of the Secretary by e-mail at 
hearing.docket@nrc.gov, or by telephone at (301) 415-1677, to request 
(1) a digital 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 https://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 
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 EIE, 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 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 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

[[Page 64390]]

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 https://www.nrc.gov/site-help/e-submittals.html, by e-mail at 
MSHD.Resource@nrc.gov, or by a toll-free call at (866) 672-7640. The 
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m., 
Eastern Time, Monday through Friday, excluding government holidays.
    Participants who believe that they have a good cause for not 
submitting documents electronically must file an exemption request, in 
accordance with 10 CFR 2.302(g), with their initial paper filing 
requesting authorization to continue to submit documents in paper 
format. Such filings must be submitted by: (1) First class mail 
addressed to the Office of the Secretary of the Commission, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: 
Rulemaking and Adjudications Staff; or (2) courier, express mail, or 
expedited delivery service to the Office of the Secretary, Sixteenth 
Floor, One White Flint North, 11555 Rockville Pike, Rockville, 
Maryland, 20852, Attention: Rulemaking and Adjudications Staff. 
Participants filing a document in this manner are responsible for 
serving the document on all other participants. Filing is considered 
complete by first-class mail as of the time of deposit in the mail, or 
by courier, express mail, or expedited delivery service upon depositing 
the document with the provider of the service. A presiding officer, 
having granted an exemption request from using E-Filing, may require a 
participant or party to use E-Filing if the presiding officer 
subsequently determines that the reason for granting the exemption from 
use of E-Filing no longer exists.
    Documents submitted in adjudicatory proceedings will appear in 
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. 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 Commission's PDR, located at One White Flint 
North, Public File Area O1F21, 11555 Rockville Pike (first floor), 
Rockville, Maryland. 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 PDR Reference staff 
at 1-800-397-4209, 301-415-4737, or by e-mail to pdr.resource@nrc.gov.

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

    Date of amendments request: August 31, 2011.
    Description of amendments request: The amendment would revise 
Technical Specification (TS) 3.4.1, ``RCS [reactor coolant system] 
Pressure, Temperature, and Flow Departure from Nuclear Boiling (DNB) 
Limits,'' the bases for TS 3.4.1 and TS 5.6.5, ``Core Operating Limits 
Report (COLR),'' by replacing the DNB numeric limits with references to 
the COLR. The proposed changes are consistent with TS Task Force (TSTF) 
change traveler TSTF-487-A, Revision 1, ``Relocate DNB Parameters to 
the COLR.''
    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. [Would the amendment involve] a significant increase in the 
probability or consequences of an accident previously evaluated?
    No.
    The proposed amendment replaces the limit values of the Reactor 
Coolant System (RCS) departure from nucleate boiling (DNB) 
parameters i.e., pressurizer pressure, RCS cold leg temperature and 
RCS flow rate in the Technical Specifications (TS) with references 
to the Core Operating Limits Report (COLR), in accordance with the 
guidance of Generic Letter 88-16, to allow these parameter limit 
values to be recalculated without a license amendment. The proposed 
amendment does not involve operation of any required structures, 
systems, or components in a manner or configuration different from 
those previously recognized or evaluated. The cycle-specific values 
in the COLR must be calculated using the NRC [Nuclear Regulatory 
Commission] approved methodologies listed in TS 5.6.5, ``Core 
Operating Limits Report (COLR).'' Replacing the RCS DNB parameter 
limits in the TS with references to the COLR will maintain existing 
operating fuel cycle analysis requirements. Because these parameter 
limits are determined using NRC-approved methodologies, the 
acceptance criteria established for the safety analyses of various 
transients and accidents will continue to be met.
    Therefore, neither the probability nor consequences of any 
accident previously evaluated will be increased by the proposed 
change.
    The proposed administrative change to remove an outdated note 
from TS 3.4.1.c and SR [surveillance requirement] 3.4.1.3 does not 
affect any analyzed accident initiators, nor does it affect the 
unit's ability to successfully respond to any previously evaluated 
accident. In addition, the proposed amendment does not change the 
operation or maintenance that is performed on plant equipment.
    Therefore, operation of the facility in accordance with the 
proposed amendment does not involve a significant increase in the 
probability of consequences of an accident previously evaluated.
    2. [Would the amendment create] the possibility of a new or 
different type of accident from any accident previously evaluated?
    No.
    The proposed amendment to replace the RCS DNB parameter limits 
in the TS with references to the COLR does not involve a physical 
alteration of the plant, nor a change or addition of a system 
function. The proposed amendment does not involve

[[Page 64391]]

operation of any required system, structure, or component in a 
manner or configuration different from those previously recognized 
or evaluated. No new failure mechanisms will be introduced by the 
proposed change.
    The proposed administrative change to remove an outdated note 
from TS 3.4.1.c and SR 3.4.1.3 does not involve a physical 
alteration to the plant (no new or different type of equipment will 
be installed) or a change in the methods governing normal plant 
operation.
    Therefore, the proposed amendment does not create the 
possibility or a new or different kind of accident from any 
previously evaluated.
    3. [Would the amendment involve] a significant reduction in a 
margin of safety?
    No.
    The proposed amendment to replace the RCS DNB parameter limits 
in the TS with references to the COLR will continue to maintain the 
margin of safety. The DNB parameter limits specified in the COLR 
will be determined based on the safety analysis of transients and 
accidents, performed using NRC-approved methodologies that show 
that, with appropriate measurement uncertainties of the parameters 
accounted for, the acceptance criteria for each of the analyzed 
transients are met. This provides the same margin of safety as the 
limit values currently specified in the TS. Any future revisions to 
the safety analyses that require prior NRC approval are identified 
per the 10 CFR [Code of Federal Regulations] 50.59 review process.
    The proposed administrative change removes an outdated note from 
TS 3.4.1.c and SR 3.4.1.3. Since this is an administrative change, 
the safety function of plant equipment and their response to any 
analyzed accident are unaffected by this proposed change and, thus, 
there is no reduction in any margin of safety.
    Therefore, the proposed amendment would 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 
amendments request involves no significant hazards consideration.
    Attorney for licensee: Carey Fleming, Sr. Counsel--Nuclear 
Generation, Constellation Generation Group, LLC, 750 East Pratt Street, 
17th floor, Baltimore, MD 21202.
    NRC Branch Chief: Nancy L. Salgado.

Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power 
Station, Unit No.1, DeWitt County, Illinois

    Date of amendment request: August 15, 2011.
    Description of amendment request: The proposed amendment would 
revise the Limiting Condition for Operation (LCO) 3.8.1, ``AC Sources--
Operating,'' through a reduction to the maximum steady state voltage 
criteria for safety-related 4.16 kV buses from 4580 V to 4300 V in 
certain Technical Specification (TS) Section 3.8.1 Surveillance 
Requirements.
    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 does not significantly increase the 
probability of an accident previously evaluated in the Updated 
Safety Analysis Report (USAR). The revised steady state voltage 
ensures that the diesel generators (DGs) and equipment powered by 
the DGs will continue to function as required to mitigate accidents 
as described in the USAR. The DGs and the equipment they power are 
part of the systems required to mitigate an accident. Mitigation 
equipment is not a factor in accident initiation.
    Therefore, the probability of a previously evaluated accident 
will not significantly increase due to operating in the proposed 
manner.
    The reduction of the DG maximum steady state voltage limit 
ensures that the DGs and the safety-related components downstream of 
the DG are operated within their design limitations; therefore, the 
consequences of an accident previously evaluated in the USAR will 
not be increased by operating in the proposed manner. The change to 
the DG maximum steady state voltage limit ensures the DGs and 
equipment powered by the DGs will perform as analyzed and mitigate 
the consequences of any accident described in the USAR.
    Therefore, the change in the maximum steady state voltage limit 
is within the bounds of previous analysis in the USAR and does not 
involve an increase in the consequences of an accident previously 
evaluated.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequence of any previously 
evaluated accident.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    This TS amendment request does not involve any changes to the 
operation, testing, or maintenance of any safety-related, or 
otherwise important to safety system. All systems that are important 
to safety will continue to be operated and maintained within their 
design bases. The proposed changes to LCO 3.8.1 will resolve a non-
conservatism, which will serve to ensure that all associated systems 
and components are operated reliably within their design 
capabilities.
    Since all systems will continue to be operated within their 
design capabilities, no new failure modes are introduced, nor is the 
possibility of a new or different kind of accident created through 
operation in the proposed manner.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed change is limited to the diesel generator maximum 
steady state voltage limit acceptance criterion in TS 3.8.1 
Surveillance Requirements. No other surveillance criterion is 
affected. The surveillance frequencies and test requirements are 
unchanged. The proposed change provides increased assurance that the 
diesel generators and equipment powered by the diesel generators 
will perform as designed.
    Therefore, the proposed amendment does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Mr. Bradley J. Fewell, Associate General 
Counsel, Exelon Generation Company, LLC, 4300 Winfield Road, 
Warrenville, IL 60555.
    NRC Branch Chief: Jacob I. Zimmerman.

FirstEnergy Nuclear Operating Company (FENOC), Docket Nos. 50-334 and 
50-412, Beaver Valley Power Station (BVPS), Unit Nos. 1 and 2, Beaver 
County, Pennsylvania

Docket No. 50-346, Davis-Besse Nuclear Power Station, Unit No. 1 
(DBNPS), Ottawa County, Ohio

Docket No. 50-440, Perry Nuclear Power Plant, Unit No. 1 (PNPP), Lake 
County, Ohio

    Date of amendment request: September 20, 2011.
    Description of amendment request: The proposed amendment would 
revise the licenses of BVPS, Unit Nos. 1 and 2, DBNPS and PNPP to 
reflect the name change of an owner licensee from ``FirstEnergy Nuclear 
Generation Corp.'' to ``FirstEnergy Nuclear Generation, LLC.'' The 
proposed amendment is administrative in nature. The proposed amendment 
will also correct errors regarding the name of FirstEnergy Nuclear 
Generation Corp in the DBNPS and PNNP Facility Operating Licenses.
    Basis for proposed no significant hazards consideration 
determination: As required by Title 10 of the Code of Federal 
Regulations (CFR), Section 50.91(a), the licensee has provided its 
analysis of the issue of no significant hazards consideration, which is 
presented below:


[[Page 64392]]


    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendment changes the name of an owner licensee. 
The proposed amendment is considered administrative in nature. The 
functions of the owner licensee will not change. There is no impact 
upon the other facility licensees. FENOC will remain the operator of 
the facilities. The proposed amendment does not alter the design, 
function, or operation of any plant equipment. As such, the accident 
and transient analyses contained in the facility updated final 
safety analysis reports will not be impacted.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed amendment is considered administrative in nature. 
The functions of the owner licensee will not change. The proposed 
amendment does not alter the design, function, or operation of any 
plant equipment.
    Therefore, the proposed change does not create the possibility 
of a new of different kind of accident from any previously 
identified.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed amendment changes the name of an owner licensee. 
The proposed amendment is considered administrative in nature. The 
functions of the owner licensee will not change. There is no impact 
upon the other facility licensees. FENOC will remain the operator of 
the facilities. The proposed amendment does not alter the design, 
function, or operation of any plant equipment. As such, the accident 
and transient analyses contained in the facility updated final 
safety analysis reports will not be impacted.
    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 
requested amendments involve no significant hazards consideration.
    Attorney for licensee: David W. Jenkins, Attorney, FirstEnergy 
Corporation, 76 South Main Street, Akron, Ohio 44308.
    NRC Branch Chief: Jacob I. Zimmerman.

Florida Power and Light Company (FPL), Docket Nos. 50-250 and 50-251, 
Turkey Point Plant, Units 3 and 4, Miami-Dade County, Florida

    Date of amendment request: May 25, 2011.
    Description of amendment request: The proposed changes would 
relocate the specifications in Section 5.2--Containment, Section 5.4--
Reactor Coolant System, and Section 5.6--Component Cyclic or Transient 
Limit, to the Updated Final Safety Analysis Report (UFSAR). Technical 
Specification (TS) 5.5.3 regarding spent fuel storage pool capacity 
would be revised to a total pool capacity limit only. This application 
also satisfies FPL commitments in Turkey Point Licensee Event Report 
05000250/2010-001-01 dated November 22, 2010, and FPL letter L-2011-032 
dated February 22, 2011.
    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:

    FPL has evaluated these TS changes to determine if a significant 
hazard is present. The No Significant Hazards Consideration 
evaluation required by 10 CFR 50.92 is provided below.
    (1) Would operation of the facility in accordance with the 
proposed amendment involve a significant increase in the probability 
or consequences of an accident previously evaluated?
    Response: No.
    The deletion of TSs 5.2, 5.4 and 5.6 with design values and 
cyclic or transient limits relocated to the FSAR, and the relocation 
of storage rack capacities in TS 5.5.3 to the FSAR are 
administrative in nature. The TS changes do not represent any 
physical change to plant systems, structures, or components, or to 
procedures established for plant operation.
    Therefore, initial conditions associated with and systems 
credited for mitigating the consequences of accidents previously 
evaluated remain unchanged.
    Therefore, facility operation in accordance with the proposed 
amendment would not involve a significant increase in the 
probability or consequences of an accident previously evaluated.
    (2) Would operation of the facility in accordance with the 
proposed amendment create the possibility of a new or different kind 
of accident from any accident previously evaluated?
    Response: No.
    The deletion of TSs 5.2, 5.4 and 5.6 with design values and 
cyclic or transient limits relocated to the FSAR, and the relocation 
of storage rack capacities in TS 5.5.3 to the FSAR are 
administrative in nature. The TS changes do not represent any 
physical change to plant systems, structures, or components, or to 
procedures established for plant operation. Because the proposed 
changes are administrative and do not alter or create a new mode of 
plant operation or configuration, the possibility of a new or 
different kind of accident is not created.
    Therefore, operation of the facility in accordance with the 
proposed amendment would not create the possibility of a new or 
different kind of accident from any accident previously evaluated.
    (3) Would operation of the facility in accordance with the 
proposed amendment involve a significant reduction in a margin of 
safety?
    Response: No.
    The deletion of TSs 5.2, 5.4 and 5.6 with design values and 
cyclic or transient limits relocated to the FSAR, and the relocation 
of storage rack capacities in TS 5.5.3 to the FSAR are 
administrative in nature. The TS changes do not represent any 
physical change to plant systems, structures, or components, or to 
procedures established for plant operation. Because the proposed 
changes are administrative and do not alter or create a new mode of 
plant operation or configuration, margins of safety are unchanged.
    Therefore, operation of the facility in accordance with the 
proposed amendment will 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 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: M.S. Ross, Attorney, Florida Power & Light, 
P.O. Box 14000, Juno Beach, Florida 33408-0420.
    NRC Branch Chief: Douglas A. Broaddus.

Florida Power and Light Company (FPL), Docket Nos. 50-250 and 50-251, 
Turkey Point Plant, Units 3 and 4, Miami-Dade County, Florida

    Date of amendment request: August 5, 2011.
    Description of amendment request: The proposed amendment would 
modify Technical Specification (TS) Surveillance Requirements (SR) 
4.8.2.1 pertaining to periodic verification of battery bank capacity 
and intercell and connection resistance.
    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:

    (a) Does the proposed change involve a significant increase in 
the probability or consequences of an accident previously evaluated?

[[Page 64393]]

    Response: No.
    The proposed changes are to the surveillance requirements only. 
The ability of the TS surveillance to ensure that the batteries have 
the capacity to perform their specified safety functions with regard 
to accident mitigation or meeting their licensing design basis 
requirements is not reduced/diminished.
    There are no design changes associated with this TS amendment. 
The DC power system/batteries will remain designed with adequate 
independency, redundancy, capacity and testability to permit the 
functioning required of the engineered safety features. The 
batteries will each continue to independently provide this capacity 
assuming a failure of a single active component.
    The proposed changes will not affect accident initiators or 
precursors, not adversely alter the design assumptions, conditions, 
and configuration of the facility or the manner in which the plant 
is operated. The proposed changes will not alter or prevent the 
ability of structures, systems and components from performing their 
intended functions to mitigate the consequences of an initiating 
event.
    The proposed changes do not physically alter safety related 
systems nor affect the way in which safety related systems perform 
their function.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    (b) 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 are to the surveillance requirements only. 
The ability of the TS surveillance to ensure that the batteries have 
the capacity to perform their specified safety functions with regard 
to accident mitigation or meeting their licensing design basis 
requirements is not reduced/diminished.
    There are no proposed design changes nor are there any changes 
in the method by which any safety related plant structure, system, 
or component (SSC) performs its specified safety function. The 
proposed changes will not affect the normal method of plant 
operation or change any operating parameters. Equipment performance 
necessary to fulfill safety analysis missions will be unaffected. 
The proposed change will not alter any assumptions required to meet 
the safety analysis acceptance criteria.
    No new accident scenarios, transient precursors, failure 
mechanisms, or limiting single failures will be introduced as a 
result of this amendment. There will be no adverse effect or 
challenges imposed on any safety related system as a result of this 
amendment.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from any accident previously 
evaluated.
    (c) Does the proposed change involve a significant reduction in 
a margin of safety?
    Response: No.
    The proposed changes do not reduce the ability of the TS 
surveillance requirements to ensure that the station batteries have 
adequate capacity to perform their engineered safety features 
functions with regard to accident mitigation and meeting their 
licensing design basis requirements. The lower battery inter-cell 
connection resistance values are more restrictive, consistent with 
design basis calculations and appropriately identified in 
maintenance procedures. In addition, the battery connections quality 
is also inherently validated by the TS SR battery performance 
testing. The new values for the battery capacity and service life 
surveillance requirements are more restrictive and more appropriate 
acceptance criteria for verifying battery performance. The reduction 
in surveillance intervals for a battery showing signs of degradation 
from 18 months to 12 months is more conservative.
    The proposed changes do not physically alter safety related 
systems. There will be no effect on those plant systems necessary to 
assure the accomplishment of protection functions. There will be no 
impact on the overpower limit, departure from nucleate boiling 
(DNBR) limits, loss of cooling accident peak cladding temperature 
(LOCA PCT), or any other margin of safety. The applicable 
radiological dose consequence acceptance criteria will continue to 
be met.
    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 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: M.S. Ross, Attorney, Florida Power & Light, 
P.O. Box 14000, Juno Beach, Florida 33408-0420.
    NRC Branch Chief: Douglas A. Broaddus.

Florida Power and Light Company (FPL), Docket Nos. 50-250 and 50-251, 
Turkey Point Plant, Units 3 and 4, Miami-Dade County, Florida

    Date of amendment request: August 17, 2011.
    Description of amendment request: The application proposes changes 
to Technical Specifications (TSs) Limiting Condition for Operation of 
TS 3.3.3.3, Tables 3.3-5, Accident Monitoring Instrumentation, High 
Range-Noble Gas Effluent Monitors, Main Steam Lines, Instrument 19d, 
and conforming changes to TS 4.3.3.3, Table 4.3-4, Accident Monitoring 
Instrumentation Surveillance Requirements, Instrument 19d.
    The Main Steam Lines High Range Noble Gas Effluent Monitor, RAD-
6426, is used in post-accident monitoring in response to the 
requirements of Regulatory Guide 1.97, Revision 3. As a Category 2, 
Type E instrument, RAD-6426 does not meet any of the Title 10 of the 
Code of Federal Regulations Section 50.36(c)(2)(ii) screening criteria 
for inclusion in the TSs Post Accident Monitoring Table. The proposed 
changes would relocate the TS and surveillance requirements for this 
instrument to the Updated Final Safety Analysis Report and related 
procedures.
    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:

    FPL has evaluated the proposed Technical Specification (TS) 
changes to determine if a significant hazard is present. The No 
Significant Hazards Consideration evaluation required by 10 CFR 
50.92 is provided below.
    1. The proposed amendment does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    The Main Steam Line High-Range Noble Gas Effluent monitor is not 
an event initiator, nor is it credited in the mitigation of any 
event. Thus, the initiating conditions and assumptions for accidents 
described in the Updated Final Safety Analysis Report (UFSAR) remain 
as analyzed. The function of the Main Steam Line High-Range Noble 
Gas Effluent monitor is to detect and quantify noble gas volumetric 
activity released from the Main Steam Safety Valves and/or the 
Atmospheric Dump Valves during and following an accident. The Main 
Steam Line monitors are used in the Emergency Plan to determine 
event action levels. The use of the monitors in the Off-Normal 
Operating Procedures, in the Emergency Operating Procedures, and 
Emergency Plan Implementing Procedures (to determine if a release is 
in progress) will not change. Relocation of the technical 
specification and surveillance requirements to the UFSAR and related 
procedures does not impact the accident analyses in any manner.
    Based on the above, the proposed change does not involve a 
significant increase in the probability or consequences of an 
accident previously evaluated.
    2. The proposed amendment does not create the possibility of a 
new or different kind of accident from any previously evaluated.
    The function of the Main Steam Line High-Range Noble Gas 
Effluent monitor is to detect and quantify noble gas volumetric 
activity released from the Main Steam Safety Valves and/or the 
Atmospheric Dump Valves during and following an accident. This 
function will not change as a result of the proposed TS changes. 
Procedural use of the monitor function, surveillance or calibration 
frequency of the monitor to determine operability will not change as 
a result of the proposed relocation of the technical specification 
and surveillance requirements to the UFSAR and related procedures.
    Based on the above, the proposed change does not create the 
possibility of a new or

[[Page 64394]]

different kind of accident from any previously evaluated.
    3. The proposed amendment does not involve a significant 
reduction in a margin of safety.
    The function of the Main Steam Line High-Range Noble Gas 
Effluent monitor is to detect and quantify noble gas volumetric 
activity released from the Main Steam Safety Valves and/or the 
Atmospheric Dump Valves during and following an accident. The 
relocation of the technical specification and surveillance 
requirements of this monitor to the UFSAR and related procedures 
does not affect the manner in which any safety limits, limiting 
safety system settings, or limiting conditions for operation are 
determined. The safety analyses are not affected by the proposed TS 
changes. The proposed changes do not result in plant operation 
outside of design bases, because the function and surveillance of 
the monitor for operability remain unchanged.
    Based on the above, operation in accordance with the proposed 
amendment would 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 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: M.S. Ross, Attorney, Florida Power & Light, 
P.O. Box 14000, Juno Beach, Florida 33408-0420.
    NRC Branch Chief: Douglas A. Broaddus.

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 Commission's Public Document Room (PDR), located at One White Flint 
North, Public File Area 01F21, 11555 Rockville Pike (first floor), 
Rockville, Maryland. 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 e-mail to pdr.resource@nrc.gov.

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

    Date of application for amendment: September 24, 2010, supplemented 
by letter dated March 4, 2011.
    Brief description of amendment: The amendment revises the licensing 
basis, specifically the Radiological Emergency Response Preparedness 
(RERP) Plan, to increase the staff augmentation times for the 
Operational and Technical Support Centers-related functions from 30 to 
60 minutes, and for Emergency Operations Facility-related functions 
from 60 to 90 minutes.
    Date of issuance: September 23, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 187.
    Facility Operating License No. NPF-43: Amendment revised the 
Operating License.
    Date of initial notice in Federal Register: November 30, 2010 (75 
FR 74093).
    The supplemental letter contained clarifying information and did 
not change the initial no significant hazards consideration 
determination, and did not expand the scope of the original 
application. The Commission's related evaluation of the amendment is 
contained in a Safety Evaluation dated September 23, 2011.
    No significant hazards consideration comments received: No.

Dominion Nuclear Connecticut, Inc., et al., Docket Nos. 50-336 and 50-
423, Millstone Power Station, Unit Nos. 2 and 3, New London County, 
Connecticut

    Date of application for amendment: July 12, 2010, as supplemented 
by letters dated August 5, 2010, September 23, 2010, November 10, 2010, 
December 13, 2010, April 4, 2011, May 17, 2011, and August 4, 2011.
    Brief description of amendment: The amendment approves the Cyber 
Security Plan (CSP) and associated implementation schedule, and revises 
the license condition regarding physical protection to reflect such 
approval. The amendment specifies that the licensee fully implement and 
maintain in effect all provisions of the Commission-approved CSP as 
required by 10 CFR 73.54.
    Date of issuance: September 30, 2011.
    Effective date: As of the date of issuance and shall be implemented 
according to the schedule conveyed in the licensee's April 4, 2011, 
letter.
    Amendment Nos.: 309 and 251.
    Renewed Facility Operating License Nos. DPR-65 and NPF-49: 
Amendment revised the respective Licenses.
    Date of initial notice in Federal Register: February 1, 2011 (76 FR 
5616). The supplemental letters contain clarifying information, did not 
change the scope of the license amendment request, did not change the 
NRC staff's initial proposed finding of no significant hazards 
consideration 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 September 30, 2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket No. 50-461, Clinton Power 
Station, Unit No. 1, DeWitt County, Illinois

    Date of application for amendment: October 8, 2010, as supplemented 
by letters dated January 6, February 24, and March 8, 2011.
    Brief description of amendment: This amendment revised technical 
specification (TS) 3.8.3, ``Diesel Fuel Oil, Lube Oil, and Starting 
Air,'' by relocating the current stored diesel fuel oil and lube oil 
numerical volume requirements from the TS to the TS Bases so that they 
may be modified under licensee control. The TS were

[[Page 64395]]

modified so that the stored diesel fuel oil and lube oil inventory 
would require that a 7-day supply be available for each diesel 
generator. Condition A and Condition B in the Action table were revised 
and Surveillance Requirements (SRs) 3.8.3.1 and 3.8.3.2 were revised to 
reflect the above change.
    Date of issuance: October 4, 2011
    Effective date: As of the date of issuance and shall be implemented 
within 60 days.
    Amendment No.: 196.
    Facility Operating License No. NPF-62: The amendment revised the 
TSs and license.
    Date of initial notice in Federal Register: May 26, 2010 (76 FR 
6833) The supplemental letters dated January 6, February 24, and March 
8, 2011 contained clarifying information and did not change the NRC 
staff's initial proposed finding of no significant hazards 
consideration.
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated October 4, 2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. 50-237 and 50-249, Dresden 
Nuclear Power Station, Units 2 and 3, Grundy County, Illinois

    Date of application for amendment: October 4, 2011, as supplemented 
by letter dated April 6, 2011.
    Brief description of amendment: The amendment revises the 
applicability of Technical Specification 3.3.1.1, ``Reactor Protection 
System Instrumentation'' Function 5 (i.e., ``Main Steam Isolation 
valve--Closure'') and Function 10 (i.e., ``Turbine Condenser Vacuum--
Low'') for Dresden Nuclear Power Station Units 2 and 3. The change 
enables the implementation of a modification that will eliminate these 
functions with the reactor switch in STARTUP while in Mode 2 with 
reactor pressure greater than or equal to 600 pounds per square inch 
(psig).
    Date of issuance: October 4, 2011.
    Effective date: As of the date of issuance and shall be implemented 
during the next outage of sufficient duration.
    Amendment Nos.: 239, 232.
    Renewed Facility Operating License Nos. DPR-19 and DPR-25: The 
amendments revised the Technical Specifications and License.
    Date of initial notice in Federal Register: February 1, 2011 (76 FR 
5619).
    The April 6, 2011, supplement contained clarifying information and 
did not change the NRC staff's initial proposed finding of no 
significant hazards consideration.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated October 4, 2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, and PSEG Nuclear, LLC, Docket No. 50-
278, Peach Bottom Atomic Power Station (PBAPS), Unit 3, York and 
Lancaster Counties, Pennsylvania

    Date of application for amendments: June 8, 2011, as supplemented 
on August 19, 2011, and September 9, 2011.
    Brief description of amendments: The amendment modifies the PBAPS 
Unit 3 Technical Specification (TS) Section 2.1.1.2 to reflect revised 
Safety Limit Minimum Critical Power Ratio (SLMCPR) values for Operating 
Cycle 19. The SLMCPR analysis establishes SLMCPR values that will 
ensure that during normal operation and during abnormal operational 
transients, at least 99.9 percent of all fuel rods in the core do not 
experience transition boiling if the limit is not violated.
    Date of issuance: September 30, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment No.: 284.
    Renewed Facility Operating License No. DPR-56: Amendment revises 
the Technical Specifications.
    Date of initial notice in Federal Register: August 22, 2011 (76 FR 
52357).
    The supplements dated August 19, 2011 and September 9, 2011, 
clarified the application, did not expand the scope of the application 
as originally noticed, and did not change the initial proposed no 
significant hazards consideration (NSHC) determination.
    The Commission's related evaluation of the amendment and final NSHC 
determination are contained in a Safety Evaluation dated September 30, 
2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, and PSEG Nuclear, LLC, Docket Nos. 50-
277 and 50-278, Peach Bottom Atomic Power Station (PBAPS), Units 2 and 
3, York and Lancaster Counties, Pennsylvania

    Date of application for amendments: June 25, 2010, as supplemented 
on August 16, 2010, December 16, 2010, January 26, 2011, and March 25, 
2011.
    Brief description of amendments: The amendment revises Technical 
Specification Surveillance Requirement (SR) 3.6.1.3, ``Primary 
Containment Isolation Valves (PCIVs),'' and SR 3.6.1.5, ``Reactor 
Building-to-Suppression Chamber Vacuum Breakers,'' to modify the 
required level for the liquid nitrogen storage tank.
    Date of issuance: September 30, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 30 days from the date of issuance.
    Amendment Nos.: 282 and 285.
    Renewed Facility Operating License Nos. DPR-44 and DPR-56: 
Amendments revised the License and Technical Specifications.
    Date of initial notice in Federal Register: November 30, 2010, (75 
FR 74094). The supplements dated August 16, 2010, December 16, 2010, 
January 26, 2011, and March 25, 2011, clarified the application, did 
not expand the scope of the application as originally noticed, and did 
not change the initial proposed no significant hazards consideration 
determination.
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated September 30, 2011.
    No significant hazards consideration comments received: No.

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

    Date of application for amendment: April 12, 2011.
    Brief description of amendment: FirstEnergy Nuclear Operating 
Company, the licensee for the Perry Nuclear Power Plant Unit No. 1 
(PNPP), requested to amend the PNPP 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 consistent with the guidance 
contained in U.S. Nuclear Regulatory Commission (NRC)-approved 
Technical Specifications Task Force Change Traveler 514 (TSTF-514). 
TSTF-514 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: October 4, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days.
    Amendment No.: 159.

[[Page 64396]]

    Facility Operating License No. NPF-58: This amendment revised the 
Technical Specifications and License.
    Date of initial notice in Federal Register: May 31, 2011 (76 FR 
31373).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated October 4, 2011.
    No significant hazards consideration comments received: No.

Nine Mile Point Nuclear Station, LLC, Docket No. 50-220, Nine Mile 
Point Nuclear Station, Unit No. 1 (NMP1), Oswego County, New York

    Date of application for amendment: September 29, 2010.
    Brief description of amendment: The amendment revises the NMP1 
Technical Specifications (TS) Sections 3/4.1.5, ``Solenoid-Actuated 
Pressure Relief Valves (Automatic Depressurization System),'' and 3/
4.2.9, ``Pressure Relief Systems-Solenoid-Actuated Pressure Relief 
Valves (Overpressurization),'' to provide for an alternative means of 
testing the main steam electromatic relief valves (ERVs). The proposed 
change allows demonstration of the capability of the valves to perform 
their safety function without requiring the ERVs to be cycled with 
reactor steam pressure while installed in the plant.
    Date of issuance: September 28, 2011.
    Effective date: As of the date of issuance to be implemented within 
90 days.
    Amendment No.: 210.
    Renewed Facility Operating License No. DPR-63: The amendment 
revises the License and TSs.
    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 September 28, 2011.
    No significant hazards consideration comments received: No.

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

    Date of amendment request: August 16, 2010, as supplemented by 
letters dated September 27, 2010, April 6, 2011, and June 30, 2011.
    Brief description of amendment: The amendment revised the Fort 
Calhoun Station, Unit 1 (FCS) Technical Specifications (TSs) to 
relocate the operating and surveillance requirements for the power-
operated relief valve and pressurizer safety valve acoustic position 
indication and tail pipe temperature from TS 2.15, ``Instrumentation 
and Control Systems,'' Table 2-5, ``Instrumentation Operating 
Requirements for Other Safety Feature Functions,'' Items 3, 4, and 5 to 
the FCS Updated Safety Analysis Report. The amendment also revised the 
surveillance requirement, TS 3.1, ``Instrumentation and Control,'' 
Table 3-3, ``Minimum Frequencies for Checks, Calibrations and Testing 
of Miscellaneous Instrumentation and Controls,'' Items 21, 23, and 24. 
Additionally, the TS Table 2-5 associated Note `e' was re-lettered to 
Note `a' and TS Table 2-5 footnote `i' to Note `c' was deleted.
    Date of issuance: September 30, 2011.
    Effective date: This license amendment is effective as of the date 
of its issuance and shall be implemented within 90 days from the date 
of issuance.
    Amendment No.: 268.
    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 
4388). The supplemental letters dated September 27, 2010, April 6, 
2011, and June 30, 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 September 30, 2011. No 
significant hazards consideration comments received: No.

Tennessee Valley Authority, Docket Nos. 50-259, 50-260, and 50-296, 
Browns Ferry Nuclear Plant, Units 1, 2, and 3, Limestone County, 
Alabama

    Date of application for amendments: November 12, 2010, as 
supplemented on February 8, May 27, June 15, and August 19, 2011.
    Description of amendment request: The changes extend the Completion 
Time (CT) specified in Technical Specification (TS) 3.8.1, ``AC 
Sources--Operating,'' for Emergency Diesel Generators (EDGs) A, B, C, 
D, 3A, 3B, 3C and 3D from 7 days to 14 days when one EDG is inoperable, 
provided a supplemental power source is available during the CT 
extension period.
    Date of issuance: October 5, 2011.
    Effective date: Date of issuance, to be implemented wit