[Federal Register Volume 76, Number 45 (Tuesday, March 8, 2011)]
[Notices]
[Pages 12763-12768]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-4829]


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NUCLEAR REGULATORY COMMISSION

[NRC-2011-0049]


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

I. 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 February 8, 2011 to February 23, 2011. The 
last biweekly notice was published on February 22, 2011 (76 FR 9821).

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

[[Page 12764]]

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.
    Written comments may be submitted by mail to the Chief, Rules, 
Announcements and Directives Branch (RADB), TWB-05-B01M, Division of 
Administrative Services, Office of Administration, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, and should cite the 
publication date and page number of this Federal Register notice. 
Written comments may also be faxed to the RADB at 301-492-3446. 
Documents may be examined, and/or copied for a fee, 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.
    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, Room O1-F21, 
11555 Rockville Pike (first floor), Rockville, Maryland 20852. Publicly 
available records will be accessible from the Agencywide Documents 
Access and Management System's (ADAMS) Public Electronic Reading Room 
on the Internet at the NRC Web site, 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 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 
[email protected], or by telephone

[[Page 12765]]

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 Commission's PDR, located at One White Flint 
North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, 
Maryland 20852. Publicly available records will be accessible from the 
ADAMS Public Electronic Reading Room on the Internet at the NRC Web 
site, 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, 301-415-4737, or by e-mail to [email protected].

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

    Date of amendment request: July 23, 2009.
    Description of amendment request: The proposed amendment would 
revise several of the Required Actions in the Ginna Technical 
Specifications that require the suspension of operations involving 
positive reactivity additions or suspension of operations that would 
cause the reduction of the reactor coolant system boron concentration. 
The proposed changes are similar to those documented in Industry 
Technical Specification Task Force (TSTF)-286, Revision 2, Define 
``Operations

[[Page 12766]]

Involving Positive Reactivity Additions.''
    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 Technical Specifications (TS) addressed in this proposed 
change prevent inadvertent addition of positive reactivity which 
could challenge the shutdown margin of the reactor core. The current 
TS contain rigid requirements that sometimes pose operational 
difficulties without significantly increasing safety. The intent of 
the change is to allow small, controlled, and safe insertions of 
positive reactivity that are now categorically prohibited to allow 
operational flexibility. These new activities could result in a 
slight change in the probability of an event occurring because 
reactor coolant system (RCS) manipulations that are currently 
prohibited would now be allowed. However, to preclude an increase in 
the probability of a reactivity addition accident, RCS manipulations 
are rigidly controlled to ensure that the reactivity remains within 
the required shutdown margin.
    The proposed change does not permit the shutdown margin to be 
reduced below that required by the TS. While the proposed change 
will permit changes in the discretionary boron concentration above 
the TS requirements, this excess concentration is not credited in 
the Updated Final Safety Analysis Report accident analysis. Because 
the initial conditions assumed in the safety analysis are preserved, 
no increase in the consequences of an accident previously evaluated 
would occur. In addition, small temperature changes in the RCS 
impose reactivity changes by means of the moderator temperature 
coefficient of reactivity. These small changes are within the 
required shutdown margin which also bounds the reactivity addition 
accident analysis ensuring there is no increase in the consequence 
of an accident previously evaluated.
    Therefore the proposed changes do 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.
    This proposed amendment allows for minor plant operational 
adjustments without adversely impacting the safety analysis required 
shut down margin. It does not involve any change to plant equipment 
or the shutdown margin requirements in the TS, and no new accident 
precursors are created.
    Therefore, the proposed change will not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The margin of safety in Modes 3, 4, 5, and 6 is preserved by the 
TS required shutdown margin which prevents a return to criticality. 
The proposed change will permit reductions in the discretionary 
shutdown margin only within the limits of the TS, thereby 
maintaining the margin of safety within the accident analysis.
    Therefore, the proposed change will not involve a significant 
reduction in the margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Carey Fleming, Sr. Counsel--Nuclear 
Generation, Constellation Group, LLC, 750 East Pratt Street, 17th 
Floor, Baltimore, MD 21202.
    NRC Branch Chief: Nancy L. Salgado.

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

    Date of amendment request: December 10, 2010.
    Description of amendment request: The proposed amendment would 
modify the Callaway Plant, Unit 1, Technical Specifications (TSs) by 
adding new Surveillance Requirement (SR) 3.3.8.6, to TS 3.3.8, 
``Emergency Exhaust System (EES) Actuation Instrumentation.'' The new 
SR would require the performance of response time testing on the 
portion of the EES required to isolate the normal fuel building 
ventilation exhaust flow path and initiate the fuel building 
ventilation isolation signal (FBVIS) mode of operation. The new SR 
3.3.8.6 would have a note excluding the radiation monitor detectors 
from response time testing. In addition, the amendment would revise TS 
Table 3.3.8-1 to indicate that the new SR 3.3.8.6 applies to automatic 
actuation Function 2, ``Automatic Actuation Logic and Actuation Relays 
(BOP ESFAS [Balance of Plant Emergency Safety Features Actuation 
System]),'' and Function 3, ``Fuel Building Exhaust Radiation--
Gaseous.'' Finally, there will be corresponding changes to the Final 
Safety Analysis Report (FSAR).
    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.
    There are no design changes associated with the proposed change. 
All design, material, and construction standards that were 
applicable prior to this amendment request will continue to be 
applicable.
    The proposed change will not affect accident initiators or 
precursors nor adversely alter the design assumptions, conditions, 
and configuration of the facility or the manner in which the plant 
is operated and maintained with respect to such initiators or 
precursors. There will be no change to fuel handling methods and 
procedures. Therefore, there will be no changes that would serve to 
increase the likelihood of occurrence of a fuel handling accident.
    The proposed change changes a performance requirement, but it 
does not physically alter safety-related systems nor affect the way 
in which safety-related systems perform their functions.
    The proposed TS change will serve to assure that the fuel 
building ventilation exhaust ESF [emergency safety feature] response 
time is tested and confirmed to be in accordance with the system 
design and consistent with the assumptions of the fuel building FHA 
[fuel handling accident] analysis (as revised). As such, the 
proposed change will not alter or prevent the capability of 
structures, systems, and components (SSCs) to perform their intended 
functions for mitigating the consequences of an accident and meeting 
applicable acceptance limits.
    The proposed change will not affect the source term used in 
evaluating the radiological consequences of a fuel handling accident 
in the fuel building. However, the Fuel Building Ventilation Exhaust 
ESF response time has been increased to 90 seconds in recognition of 
the total delay times involved in the generation of a fuel building 
ventilation isolation signal (FBVIS) and the times required for 
actuated components to change state to their required safety 
configurations. Consequently, the fuel handling accident 
radiological consequences as reported in FSAR [Final Safety Analysis 
Report] Table 15.7-8 have increased. However, the increases are much 
less than the upper limit of ``minimal'' as defined pursuant to 10 
CFR 50.59(c)(2)(iii) and NEI [Nuclear Energy Institute] 96-07 
Revision 1 [``Guidelines for 10 CFR 50.59 Implementation,'' November 
2000]. Therefore, there is no significant increase in the calculated 
consequences of a postulated design basis fuel handling accident in 
the fuel building. The applicable radiological dose criteria of 10 
CFR 100.11, 10 CFR 50 Appendix A General Design Criterion 19, and 
SRP [NUREG-0800, ``Standard Review Plan for the Review of Safety 
Analysis Reports for Nuclear Power Plants: LWR [Light-Water-Reactor] 
Edition''] 15.7.4 will continue to be met. New SR 3.3.8.6 is added 
to ensure system performance consistent with the accident analyses 
and associated dose calculations (as revised).

[[Page 12767]]

    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.
    With respect to any new or different kind of accident, there are 
no proposed design changes nor are there any changes in the method 
by which any safety-related plant SSC performs its specified safety 
function. The proposed change will not affect the normal method of 
plant operation or change any operating parameters. No new accident 
scenarios, transient precursors, failure mechanisms, or limiting 
single failures will be introduced as a result of this amendment.
    The proposed amendment will not alter the design or performance 
of the 7300 Process Protection System, Nuclear Instrumentation 
System, Solid State Protection System, BOP ESFAS, MSFIS [Main Steam 
and Feed Isolation System], or LSELS [Load Shedding and Emergency 
Load Sequencing] used in the plant protection systems.
    The proposed change does not, therefore, create the possibility 
of a new or different accident from any accident previously 
evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    There will be no effect on those plant systems necessary to 
assure the accomplishment of protection functions associated with 
reactor operation or the reactor coolant system. There will be no 
impact on the overpower limit, departure from nucleate boiling ratio 
(DNBR) limits, heat flux hot channel factor (FQ), nuclear 
enthalpy rise hot channel factor (F[Delta]H), loss of coolant 
accident peak cladding temperature (LOCA PCT), peak local power 
density, or any other limit and associated margin of safety. 
Required shutdown margins in the COLR [Core Operating Limits Report] 
will not be changed.
    The proposed change does not eliminate any surveillances or 
alter the frequency of surveillances required by the Technical 
Specifications. The proposed change would add a new Technical 
Specification Surveillance Requirement for assuring the satisfactory 
performance of the fuel building ventilation exhaust ESF function in 
response to a[n] FBVIS. The accident analysis for a fuel handling 
accident in the fuel building was re-performed to support the 
proposed Fuel Building Ventilation Exhaust ESF response time, and 
this reanalysis demonstrated that the acceptance criteria continue 
to be met with only a slight increase in radiological consequences 
(i.e., less than one percent).
    Therefore, the proposed change does not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: John O'Neill, Esq., Pillsbury Winthrop Shaw 
Pittman LLP, 2300 N Street, NW., Washington, DC 20037.
    NRC Branch Chief: Michael T. Markley.

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, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, 
Maryland 20852. Publicly available records will be accessible from the 
Agencywide Documents Access and Management System (ADAMS) Public 
Electronic Reading Room on the Internet at the NRC Web site, 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].

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

    Date of application for amendments: November 23, 2009, as 
supplemented by letters dated January 26, April 22, July 23, August 9, 
October 29, November 19, December 30, 2010, and January 14, January 18, 
January 28, February 11, and February 15, 2011.
    Brief description of amendments: The amendments revise the 
licensing basis and the Technical Specifications to allow the use of 
AREVA Advanced CE-14 HTP fuel in the Calvert Cliffs reactors. The AREVA 
Advanced CE-14 HTP fuel design consists of standard uranium dioxide 
(U02) fuel pellets with gadolinium oxide 
(Gd203) burnable poison and M5 cladding.
    Date of issuance: February 18, 2011.
    Effective date: As of the date of issuance to be implemented within 
30 days.
    Amendment Nos.: 297 and 273.
    Renewed Facility Operating License Nos. DPR-53 and DPR-69: 
Amendments revised the License and Technical Specifications.
    Date of initial notice in Federal Register: May 4, 2010 (75 FR 
23810). The letters dated July 23, August 9, October 29, November 19, 
December 30, 2010, and January 14, January 18, January 28, February 11, 
and February 15, 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 these amendments is 
contained in a Safety Evaluation dated February 18, 2011.
    No significant hazards consideration comments received: No.

Entergy Operations, Inc., Docket No. 50-382, Waterford Steam Electric 
Station, Unit 3, St Charles Parish, Louisiana

    Date of amendment request: February 22, 2010, as supplemented by 
letters dated December 3, 2010, and January 19, 2011.
    Brief description of amendment: The amendment modified Technical 
Specification (TS) \3/4\.9.4, ``Containment Building Penetrations,'' to 
allow alternative means of penetration closure during core alterations 
or irradiated fuel

[[Page 12768]]

movement while in refueling operations. In addition, certain 
improvements to this TS, as well as the elimination of TS \3/4\.9.9, 
``Containment Purge Valve Isolation System,'' were made. The changes 
are similar to Revision 3 of NUREG-1432, ``Standard Technical 
Specifications, Combustion Engineering Plants.''
    Date of issuance: February 23, 2011.
    Effective date: As of the date of issuance and shall be implemented 
90 days from the date of issuance.
    Amendment No.: 231.
    Facility Operating License No. NPF-38: The amendment revised the 
Facility Operating License and Technical Specifications.
    Date of initial notice in Federal Register: May 4, 2010 (75 FR 
23813). The supplemental letters dated December 3, 2010, and January 
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 February 23, 2011.
    No significant hazards consideration comments received: No.

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

    Date of application for amendment: February 15, 2010, as 
supplemented by letter dated May 21, 2010.
    Brief description of amendment: The amendment relocates selected 
Surveillance Requirement frequencies from the Clinton Power Station, 
(CPS) Unit No. 1, technical specifications (TSs) to a licensee-
controlled program. This change is based on the NRC-approved Industry 
Technical Specifications Task Force (TSTF) change TSTF-425, ``Relocate 
Surveillance Frequencies to Licensee Control--Risk Informed Technical 
Specification Task Force (RITSTF) Initiative 5b,'' Revision 3, 
(Agencywide Documents Access and Management System (ADAMS) Accession 
Package No. ML090850642). Furthermore, some plant-specific deviations 
from TSTF-425 were also incorporated into the CPS TSs.
    Date of issuance: February 15, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days.
    Amendment No.: 192.
    Facility Operating License No. NPF-62: The amendment revised the 
Technical Specifications and License.
    Date of initial notice in Federal Register: May 4, 2010 (75 FR 
23814). The May 21, 2010, 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 amendment is contained 
in a Safety Evaluation dated February 15, 2011.
    No significant hazards consideration comments received: No.

Exelon Generation Company, LLC, Docket Nos. 50-254 and 50-265, Quad 
Cities Nuclear Power Station, Units 1 and 2, Rock Island County,

    Date of amendment request: February 16, 2010, as supplemented by 
letter dated June 22, 2010.
    Brief description of amendments: The amendments relocate selected 
Surveillance Requirement frequencies from the Quad Cities Nuclear Power 
Station Units 1 and 2 Technical Specifications (TSs) to a licensee-
controlled program. This change is based on the NRC-approved Industry 
Technical Specifications Task Force (TSTF) change TSTF-425, ``Relocate 
Surveillance Frequencies to Licensee Control--Risk Informed Technical 
Specification Task Force (RITSTF) Initiative 5b,'' Revision 3, 
(Agencywide Documents Access and Management System (ADAMS) Accession 
Package No. ML090850642).
    Date of issuance: February 18, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days.
    Amendment Nos.: 248/243.
    Renewed Facility Operating License Nos. DPR-29 and DPR-30: The 
amendments revised the Technical Specifications and License.
    Date of initial notice in Federal Register: April 20, 2010 (75 FR 
20638). The June 22, 2010, 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 February 18, 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: February 24, 2010, as 
supplemented September 20, 2010, and November 5, 2010.
    Brief description of amendment: The amendment revises the Technical 
Specification (TS) 3.7.11, ``Control Room Emergency Air Temperature 
Control System (CREATCS).'' The amendment will only be applicable 
during plant modifications to upgrade the CREATCS chillers. This ``one-
time'' TS change will be implemented during WBN Unit 1 Cycles 10 and 11 
beginning March 1, 2011, and ending April 30, 2012.
    Date of issuance: February 8, 2011.
    Effective date: As of the date of issuance and shall be implemented 
no later than 90 days from date of issuance.
    Amendment No.: 85.
    Facility Operating License No. NPF-90: Amendment revised the 
License and TSs.
    Date of initial notice in Federal Register: June 1, 2010 (75 FR 
30447). The supplements dated September 20 and November 5, 2010, 
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 February 8, 2011.
    No significant hazards consideration comments received: No.

    Dated at Rockville, Maryland, this 24th day of February 2011.

    For the Nuclear Regulatory Commission.
Joseph G. Giitter,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2011-4829 Filed 3-7-11; 8:45 am]
BILLING CODE 7590-01-P