[Federal Register Volume 76, Number 229 (Tuesday, November 29, 2011)]
[Notices]
[Pages 73727-73733]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2011-30525]


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NUCLEAR REGULATORY COMMISSION

[NRC-2011-0274]


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 November 3, 2011 to November 16, 2011. The 
last biweekly notice was published on November 15, 2011 (76 FR 70768).

ADDRESSES: Please include Docket ID NRC-2011-0274 in the subject line 
of your comments. For additional instructions on submitting comments 
and instructions on accessing documents related to this action, see 
``Submitting Comments and Accessing Information'' in the SUPPLEMENTARY 
INFORMATION section of this document. You may submit comments by any 
one of the following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for documents filed under Docket ID NRC-
2011-0274. Address questions about NRC dockets to Carol Gallagher, 
telephone: (301) 492-3668; email: [email protected].
     Mail comments to: Cindy Bladey, Chief, Rules, 
Announcements, and Directives Branch (RADB), Office of Administration, 
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555-0001.
     Fax comments to: RADB at (301) 492-3446.

SUPPLEMENTARY INFORMATION:

Submitting Comments and Accessing Information

    Comments submitted in writing or in electronic form will be posted 
on the NRC Web site and on the Federal rulemaking Web site, http://www.regulations.gov. Because your comments will not be edited to remove 
any identifying or contact information, the NRC cautions you against 
including any information in your submission that you do not want to be 
publicly disclosed.
    The NRC requests that any party soliciting or aggregating comments 
received from other persons for submission to the NRC inform those 
persons that the NRC will not edit their comments to remove any 
identifying or contact information, and therefore, they should not 
include any information in their comments that they do not want 
publicly disclosed.
    You can access publicly available documents related to this 
document 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 available online in the NRC Library at http://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain entry into ADAMS, 
which provides text and image files of the NRC's public documents. If 
you do not have access to ADAMS or if there are problems in accessing 
the documents located in ADAMS, contact the NRC's PDR reference staff 
at 1-(800) 397-4209, (301) 415-4737, or by email to 
[email protected].
     Federal Rulemaking Web site: Public comments and 
supporting materials related to this notice can be found at http://www.regulations.gov by searching on Docket ID NRC-2011-0274.

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

[[Page 73728]]

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; (2) 
create the possibility of a new or different kind of accident from any 
accident previously evaluated; or (3) involve a significant reduction 
in a margin of safety. The basis for this proposed determination for 
each amendment request is shown below.
    The Commission is seeking public comments on this proposed 
determination. Any comments received within 30 days after the date of 
publication of this notice will be considered in making any final 
determination.
    Normally, the Commission will not issue the amendment until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment 
involves no significant hazards consideration. In addition, the 
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day 
comment period such that failure to act in a timely way would result, 
for example in derating or shutdown of the facility. Should the 
Commission take action prior to the expiration of either the comment 
period or the notice period, it will publish in the Federal Register a 
notice of issuance. Should the Commission make a final No Significant 
Hazards Consideration Determination, any hearing will take place after 
issuance. The Commission expects that the need to take this action will 
occur very infrequently.
    Within 60 days after the date of publication of this notice, any 
person(s) whose interest may be affected by this action may file a 
request for a hearing and a petition to intervene with respect to 
issuance of the amendment to the subject facility operating license. 
Requests for a hearing and a petition for leave to intervene shall be 
filed in accordance with the Commission's ``Rules of Practice for 
Domestic Licensing Proceedings'' in 10 CFR part 2. Interested person(s) 
should consult a current copy of 10 CFR 2.309, which is available at 
the NRC's PDR, located at One White Flint North, 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 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, 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 email at [email protected], 
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

[[Page 73729]]

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 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 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 email notice confirming receipt of the document. The 
E-Filing system also distributes an email notice that provides access 
to the document to the NRC Office of the General Counsel and any others 
who have advised the Office of the Secretary that they wish to 
participate in the proceeding, so that the filer need not serve the 
documents on those participants separately. Therefore, applicants and 
other participants (or their counsel or representative) must apply for 
and receive a digital ID certificate before a hearing request/petition 
to intervene is filed so that they can obtain access to the document 
via the E-Filing system.
    A person filing electronically using the agency's adjudicatory E-
Filing system may seek assistance by contacting the NRC Meta System 
Help Desk through the ``Contact Us'' link located on the NRC Web site 
at http://www.nrc.gov/site-help/e-submittals.html, by email at 
[email protected], 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 
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, Public File Area O1 F21, 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 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 email to 
[email protected].
    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 amendment request: August 8, 2011.
    Description of amendment request: The amendment would modify 
Technical Specification 3.8.1, ``AC Sources--Operating,'' Surveillance 
Requirement (SR) 3.8.1.11 by revising the required power factor value 
to be achieved by the diesel generators (DGs) during conduct of the 
surveillance test. The proposed change would also modify the existing 
note in SR 3.8.1.11 to address offsite power grid conditions that could 
exist during surveillance testing.
    Basis for proposed no significant hazards consideration 
determination: As required by 10 CFR 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

    1. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    No.
    The first part of the proposed change to SR 3.8.1.11 corrects 
the current non-conservative DG power factor value and aligns it 
with the power factor value calculated in the design basis 
calculation for the worst case design basis accident electrical 
loads. This part of

[[Page 73730]]

the proposed change does not affect any analyzed accident 
initiators, nor does it affect the units' ability to successfully 
respond to any previously evaluated accident. Testing at a more 
conservative power factor value better demonstrates the DG's ability 
to handle expected electrical loads during worst case design basis 
accidents. In addition, this part of the proposed change does not 
alter any existing radiological assumptions used in the accident 
evaluations nor does it change the operation or maintenance 
performed on operating equipment.
    The second part of the proposed change modifies an existing note 
in SR 3.8.1.11 to allow the required DG power factor not to be 
achieved during testing when certain grid conditions exist. This 
exception exists to prevent testing the DG in a condition that might 
do damage to the DG or cause bus voltage to exceed voltage limits. 
This proposed change does not affect any analyzed accident 
initiators, nor does it affect the units' ability to successfully 
respond to any previously evaluated accident. Additionally there is 
no affect on any existing radiological assumptions used in the 
accident evaluations nor does it change the operation or maintenance 
performed on operating equipment.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.
    2. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    No.
    The first part of the proposed change to SR 3.8.1.11 corrects 
the current non-conservative DG power factor value and aligns it 
with the power factor value calculated in the design basis 
calculation for the worst case design basis accident electrical 
loads. Testing to a more conservative power factor better 
demonstrates the DG ability to handle expected electrical loads 
during worst case design basis accidents. This part of the proposed 
change does not involve a modification to the physical configuration 
of the units nor does it involve any change in the methods governing 
normal plant operation. The proposed change does not impose any new 
or different requirements that would introduce a new accident 
initiator, accident precursor, or malfunction mechanism. 
Additionally there is no change in the types of, or increase in the 
amounts of, any effluent that may be released offsite and there is 
no increase in individual or cumulative occupational exposure as a 
result of this proposed change. As such, this part of the proposed 
change does not introduce a mechanism for initiating a new or 
different accident than those previously analyzed.
    The second part of the proposed change modifies an existing note 
in SR 3.8.1.11 to allow the required DG power factor not to be 
achieved during testing when certain grid conditions exist. This 
exception exists to prevent testing the DG in a condition that might 
do damage to the DG or cause bus voltage to exceed voltage limits. 
This part of the proposed change does not involve a modification to 
the physical configuration of the units nor does it involve any 
change in the methods governing normal plant operation. The proposed 
change does not impose any new or different requirements that would 
introduce a new accident initiator, accident precursor, or 
malfunction mechanism. Additionally there is no change in the types 
or increase in the amounts of any effluent that may be released 
offsite and there is no increase in the individual or cumulative 
occupational exposure as a result of this proposed change. As such, 
this part of the proposed change does not introduce a mechanism for 
initiating a new or different accident than those previously 
analyzed.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    No.
    The first part of the proposed change to SR 3.8.1.11 corrects 
the current non-conservative DG power factor value and aligns it 
with the power factor value calculated in the design basis 
calculation for the worst-case design basis accident electrical 
loads. Testing to a more conservative power factor more fully 
demonstrates the DG ability to handle expected electrical loads 
during worst case design basis accidents. This part of the proposed 
change does not involve any modification to the physical 
configuration of the operating units and does not alter equipment 
operation. As such the safety functions of plant equipment and their 
response to any analyzed accident scenario are unaffected by this 
proposed change and thus there is no reduction in any margin of 
safety.
    The second part of the proposed change modifies an existing note 
in SR 3.8.1.11 to allow the required DG power factor not to be 
achieved during testing when certain grid conditions exist. This 
exception exists to prevent testing the DG in a condition that might 
do damage to the DG or cause bus voltage to exceed voltage limits. 
This part of the proposed change does not involve any modification 
to the physical configuration of the operating units and does not 
alter equipment operation. As such the safety functions of plant 
equipment and their response to any analyzed accident scenario are 
unaffected by this proposed change and thus there is no reduction in 
any margin of safety.
    Therefore, the proposed change does not involve a significant 
reduction in the margin of safety for the operation of each unit.

    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.
    Dominion Nuclear Connecticut, Inc., Docket No. 50-336, Millstone 
Power Station, Unit No. 2, New London County, Connecticut.
    Date of amendment request: September 21, 2011.
    Description of amendment request: The proposed amendment would 
revise the Millstone Power Station, Unit No. 2 (MPS2) Technical 
Specification (TS) surveillance requirements for snubbers to conform to 
the revised MPS2 inservice inspection (ISI) program, move the specific 
surveillance requirements of TS 3/4.7.8, ``Snubbers,'' to the ``Snubber 
Examination, Testing, and Service Life Monitoring Program,'' add a 
reference to the program in the administrative controls section of the 
MPS2 TSs, and make administrative changes to TS 3/4.7.8.
    Basis for proposed no significant hazards consideration 
determination: As required by Title 10 of the Code of Federal 
Regulations (10 CFR) part 50, Section 50.91(a), the licensee has 
provided its analysis of the issue of no significant hazards 
consideration, which is presented below:

Criterion 1

    Will operation of the facility in accordance with the proposed 
change involve a significant increase in the probability or 
consequences of an accident previously evaluated?
    Response: No.
    The proposed changes would revise SR [surveillance requirement] 
4.7.8 to conform the TSs to the revised ISI program for snubbers. 
Snubber examination, testing and service life monitoring will 
continue to meet the requirements of 10 CFR 50.55a(g) except where 
the NRC [Nuclear Regulatory Commission] has granted specific written 
relief, pursuant to 10 CFR 50.55a(g)(6)(i), or authorized 
alternatives pursuant to 10 CFR 50.55a(a)(3).
    Snubber examination, testing and service life monitoring is not 
an initiator of any accident previously evaluated. Therefore, the 
probability of an accident previously evaluated is not significantly 
increased.
    Snubbers will continue to be demonstrated OPERABLE by 
performance of a program for examination, testing and service life 
monitoring in compliance with 10 CFR 50.55a or authorized 
alternatives. The proposed change to TS ACTION 3.7.8 for inoperable 
snubbers is administrative in nature and is required for consistency 
with the proposed change to SR 4.7.8. Therefore, the proposed change 
does not adversely affect plant operations, design functions or 
analyses that verify the capability of systems, structures, and 
components to perform their design functions. The consequences of 
accidents previously evaluated are not significantly increased.
    Therefore, the proposed changes do not involve a significant 
increase in the probability or consequences of an accident 
previously evaluated.

[[Page 73731]]

Criterion 2

    Will operation of the facility in accordance with this proposed 
change create the possibility of a new or different kind of accident 
from any accident previously evaluated?
    Response: No.
    The proposed changes do not involve any physical alteration of 
plant equipment. The proposed changes do not change the method by 
which any safety-related system performs its function. As such, no 
new or different types of equipment will be installed, and the basic 
operation of installed equipment is unchanged. The methods governing 
plant operation and testing remain consistent with current safety 
analysis assumptions.
    Therefore, the proposed changes do not create the possibility of 
a new or different kind of accident from any previously evaluated.

Criterion 3

    Will operation of the facility in accordance with this proposed 
change involve a significant reduction in the margin of safety?
    Response: No.
    The proposed changes ensure snubber examination, testing and 
service life monitoring will continue to meet the requirements of 10 
CFR 50.55a(g) except where the NRC has granted specific written 
relief, pursuant to 10 CFR 50.55a(g)(6)(i), or authorized 
alternatives pursuant to 10 CFR 50.55a(a)(3). Snubbers will continue 
to be demonstrated OPERABLE by performance of a program for 
examination, testing and service life monitoring in compliance with 
10 CFR 50.55a or authorized alternatives. The proposed change to TS 
ACTION 3.7.8 for inoperable snubbers is administrative in nature and 
is required for consistency with the proposed change to SR 4.7.8.
    Therefore, the proposed changes do not involve a significant 
reduction in a margin of safety.

    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    Attorney for licensee: Lillian M. Cuoco, Senior Counsel, Dominion 
Resources Services, Inc., 120 Tredegar Street, RS-2, Richmond, VA 
23219; NRC Branch Chief: Harold K. Chernoff.
    Indiana Michigan Power Company (the licensee), Docket No. 50-316, 
Donald C. Cook Nuclear Plant, Unit 2 (DCCNP-2), Berrien County, 
Michigan;
    Date of amendment request: September 29, 2011.
    Description of amendment request: The proposed amendment would 
revise Technical Specification (TS) 4.2.1, adding Optimized 
ZIRLOTM fuel rods to the fuel matrix in addition to Zircaloy 
or ZIRLOTM fuel rods that are currently in use. The proposed 
amendment would also add a Westinghouse topical report regarding 
Optimized ZIRLOTM as reference 8 in TS 5.6.5.b, which lists 
the analytical methods used to determine the core operating limits.
    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 would allow the use of Optimized 
ZIRLOTM clad nuclear fuel in the reactors. The NRC[-
]approved topical report WCAP-12610-P-A and CENPD-404-P-A, Addendum 
1-A ``Optimized ZIRLOTM,'' prepared by Westinghouse 
Electric Company LLC (Westinghouse), addresses Optimized 
ZIRLOTM and demonstrates that Optimized 
ZIRLOTM has essentially the same properties as currently 
licensed ZIRLOTM. The fuel cladding itself is not an 
accident initiator and does not affect accident probability. Use of 
Optimized ZIRLOTM fuel cladding has been shown to meet 
all 10 CFR 50.46 acceptance criteria and, therefore, will not 
increase the consequences of an accident.
    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.
    Use of Optimized ZIRLOTM clad fuel will not result in 
changes in the operation or configuration of the facility. Topical 
Report WCAP-12610-P-A and CENPD-404-P-A demonstrated that the 
material properties of Optimized ZIRLOTM are similar to 
those of standard ZIRLOTM. Therefore, Optimized 
ZIRLOTM fuel rod cladding will perform similarly to those 
fabricated from standard ZIRLOTM, thus precluding the 
possibility of the fuel becoming an accident initiator and causing a 
new or different type of accident.
    Therefore, the proposed change does not create the possibility 
of a new or different kind of accident from any previously 
evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed change will not involve a significant reduction in 
the margin of safety because it has been demonstrated that the 
material properties of the Optimized ZIRLOTM are not 
significantly different from those of standard ZIRLOTM. 
Optimized ZIRLOTM is expected to perform similarly to 
standard ZIRLOTM for all normal operating and accident 
scenarios, including both loss of coolant accident (LOCA) and non-
LOCA scenarios. For LOCA scenarios, where the slight difference in 
Optimized ZIRLOTM material properties relative to 
standard ZIRLOTM could have some impact on the overall 
accident scenario, plant-specific LOCA analyses using Optimized 
ZIRLOTM properties will be performed prior to the use of 
fuel assemblies with fuel rods containing Optimized 
ZIRLOTM. These LOCA analyses will demonstrate that the 
acceptance criteria of 10 CFR 50.46 will be satisfied when Optimized 
ZIRLOTM fuel rod cladding is implemented.
    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: James M. Petro, Jr., Senior Nuclear Counsel, 
Indiana Michigan Power Company, One Cook Place, Bridgman, MI 49106.
    NRC Acting Branch Chief: Thomas J. Wengert.

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

[[Page 73732]]

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 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 email to 
[email protected].
    Entergy Nuclear Vermont Yankee, LLC and Entergy Nuclear Operations, 
Inc., Docket No. 50-271, Vermont Yankee Nuclear Power Station, Vernon, 
Vermont;
    Date of amendment request: December 21, 2010 as supplemented by 
letter dated May 16, 2011.
    Description of amendment request: The amendment would revise 
Technical Specifications Section 3.6.A ``Pressure and Temperature 
Limitation'' to reflect the pressure and temperature limits for the 
reactor coolant system through, approximately the end of the 
prospective 20-year renewed license period, depending on the plant 
capacity factor.
    Date of Issuance: November 4, 2011.
    Effective date: As of the date of issuance, and shall be 
implemented within 60 days.
    Amendment No.: 250.
    Facility Operating License No. DPR-28: Amendment revised the 
License and Technical Specifications.
    Date of initial notice in Federal Register: February 22, 2011 (76 
FR 9823). The supplemental letter dated May 16, 2011, provided 
additional information that clarified the application, did not expand 
the scope of the application as originally noticed, and did not change 
the staff's original proposed no significant hazards consideration 
determination. The Commision's related evaluation of this amendment is 
contained in a Safety Evaluation dated dated November 4, 2011. No 
significant hazards consideration comments received: No.
    Entergy Operations, Inc., Docket No. 50-313, Arkansas Nuclear One, 
Unit No. 1, Pope County, Arkansas;
    Date of amendment request: April 29, 2011.
    Brief description of amendment: The amendment revised Technical 
Specification (TS) 3.4.15, ``RCS [Reactor Coolant System] Leakage 
Detection Instrumentation,'' to define a new time limit for restoring 
inoperable 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 changes are consistent with NRC-approved 
Revision 3 to Technical Specification Task Force (TSTF) Standard 
Technical Specification Change Traveler TSTF-513, ``Revise PWR 
Operability Requirements and Actions for RCS Leakage Instrumentation.''
    Date of issuance: November 16, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 246.
    Renewed Facility Operating License No. DPR-51: Amendment revised 
the Technical Specifications/license.
    Date of initial notice in Federal Register: September 6, 2011 (76 
FR 55128).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated November 16, 2011. No significant hazards 
consideration comments received: No.
    Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, 
Donald C. Cook Nuclear Plant, Units 1 and 2, Berrien County, Michigan;
    Date of application for amendment: May 3, 2011.
    Brief description of amendment: The amendment revises Technical 
Specifications Section 3.4.15 regarding reactor coolant leakage 
detection instrumentation to be consistent with Revision 3 of Technical 
Specification Task Force (TSTF) Standard Technical Specification Change 
Traveler, TSTF-513, ``Revise PWR [Pressurized Water Reactor] 
Operability Requirements and Actions for RCS [Reactor Coolant System] 
Leakage Instrumentation.''
    Date of issuance: November 1, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 90 days from the date of issuance.
    Amendment No.: 317 (for Unit 1) and 300 (for Unit 2).
    Facility Operating License Nos. DPR-58 and DPR-74: Amendments 
revised the Renewed Operating License and Technical Specifications.
    Date of initial notice in Federal Register: June 14, 2011 (76 FR 
34768).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated November 1, 2011.
    No significant hazards consideration comments received: No.
    Indiana Michigan Power Company, Docket Nos. 50-315 and 50-316, 
Donald C. Cook Nuclear Plant, Units 1 and 2, Berrien County, Michigan;
    Date of application for amendment: March 18, 2011.
    Brief description of amendment: The amendment revises the Technical 
Specifications (TS) in accordance with the previously approved 
Technical Specification Task Force (TSTF) Change Traveler TSTF-491. 
Specifically the amendment changes Surveillance Requirements 3.7.2.1, 
3.7.3.1, and 3.7.3.2 by relocating the closure times for the Steam 
Generator Stop Valves, Main Feed Isolation Valves, and Main Feed 
Regulation Valves from the TS to the licensee-controlled TS Bases 
document.
    Date of issuance: November 3, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 120 days from the date of issuance.
    Amendment Nos.: 318 (for Unit 1) and 301 (for Unit 2).
    Facility Operating License Nos. DPR-58 and DPR-74: Amendments 
revised the Renewed Operating License and Technical Specifications.
    Date of initial notice in Federal Register: May 17, 2011 (76 FR 
28474).
    The Commission's related evaluation of the amendment is contained 
in a Safety Evaluation dated November 3, 2011.
    No significant hazards consideration comments received: No.
    Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 
50-425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County, 
Georgia;
    Date of application for amendments: March 14, 2011
    Brief description of amendments: The amendments revised the 
Technical Specifications (TS) ``RHR and Coolant Circulation-Low Water 
Level,'' to allow one RHR loop to be operable for up to 2 hours for 
surveillance testing provided the other RHR loop is operable and in 
operation. This revision is consistent with the Industry/Technical 
Specification Task Force (TSTF) Standard Technical Specification 
Traveler TSTF-361-A, Revision 2, ``Allow standby SDC [shutdown 
cooling]/RHR[residual heat removal]/DHR [decay heat removal] loop to 
inoperable to support testing.''
    Date of issuance: November 9, 2011.

[[Page 73733]]

    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos.: 163/145.
    Facility Operating License Nos. NPF-68 and NPF-81: Amendments 
revised the licenses and the technical specifications.
    Date of initial notice in Federal Register: May 17, 2011 (76 FR 
28476).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated November 9, 2011.
    No significant hazards consideration comments received: No.
    Southern Nuclear Operating Company, Inc., Docket Nos. 50-424 and 
50-425, Vogtle Electric Generating Plant, Units 1 and 2, Burke County, 
Georgia;
    Date of application for amendments: April 29, 2011
    Brief description of amendments: The amendments revised the 
Technical Specifications (TSs) ``RCS [reactor coolant system] Leakage 
Detection Instrumentation,'' to define a new time limit for restoring 
inoperable RCS leakage detection instrument to operable status and 
establish alternate methods of monitoring RCS leakage when one or more 
required monitors are inoperable. This revision is consistent with the 
Industry/Technical Specification Task Force (TSTF) standard technical 
specification traveler TSTF-513-A, ``Revise PWR [pressurized water 
reactor] Operability Requirements and Actions for RCS Leakage 
[Detection] Instrumentation.''
    Date of issuance: November 10, 2011.
    Effective date: As of the date of issuance and shall be implemented 
within 60 days from the date of issuance.
    Amendment Nos.: 164/146.
    Facility Operating License Nos. NPF-68 and NPF-81: Amendments 
revised the licenses and the technical specifications.
    Date of initial notice in Federal Register: June 14, 2011 (76 FR 
34768).
    The Commission's related evaluation of the amendments is contained 
in a Safety Evaluation dated November 10, 2011.
    No significant hazards consideration comments received: No.

    For the Nuclear Regulatory Commission.

    Dated at Rockville, Maryland, this 17th day of November 2011.
Michele G. Evans,
Director, Division of Operating Reactor Licensing, Office of Nuclear 
Reactor Regulation.
[FR Doc. 2011-30525 Filed 11-28-11; 8:45 am]
BILLING CODE 7590-01-P