[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