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{{#Wiki_filter:44614 Federal Register/Vol. 76, No. 143/Tuesday, July 26, 2011/Notices fixtures, and electronic equipment. For many of these incidental items, U.S.  
{{#Wiki_filter:44614                           Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices fixtures, and electronic equipment. For                 costing $10,000 or less used in and                  their comments that they do not want many of these incidental items, U.S.                     incorporated into the project. With this              publicly disclosed.
 
manufactured alternatives are not                       exemption, the agency hereby                            You may submit comments by any always readily or reasonably available.                 establishes a $1.5M ceiling for the total            one of the following methods.
manufactured alternatives are not  
The miscellaneous character of these                     allowable value of de minimis
 
* Federal Rulemaking Web site: Go to manufactured goods, together with their                 exemptions used on this project.                      http://www.regulations.gov and search low individual cost, characterize them                                                                         for documents filed under Docket ID Dated: July 7, 2011.
always readily or reasonably available.  
as items incidental to the project.                                                                           NRC-NRC-2011-0167. Address Lawrence Rudolph, Requiring individual exemptions for                                                                           questions about NRC dockets to Carol General Counsel.                                      Gallagher 301-492-3668; e-mail low cost, incidental items would be time prohibitive and overly burdensome                   [FR Doc. 2011-18643 Filed 7-25-11; 8:45 am]          Carol.Gallagher@nrc.gov.
 
for the awardee (University of Alaska,                  BILLING CODE 7555-01-P
The miscellaneous character of these  
* Mail comments to: Chief, Rules, Fairbanks), subcontractor (shipyard) and                                                                       Announcements, and Directives Branch for NSF. Such a de minimis exemption                                                                           (RADB), Office of Administration, Mail allows the award recipients to focus                     NUCLEAR REGULATORY                                    Stop: TWB-05-B01M, U.S. Nuclear their efforts on the major manufactured                 COMMISSION                                            Regulatory Commission, Washington, goods within the ARRV project. The                                                                             DC 20555-0001.
 
manufactured goods, together with their  
 
low individual cost, characterize them  
 
as items incidental to the project.  
 
Requiring individual exemptions for  
 
low cost, incidental items would be  
 
time prohibitive and overly burdensome  
 
for the awardee (University of Alaska, Fairbanks), subcontractor (shipyard) and  
 
for NSF. Such a de minimis exemption  
 
allows the award recipients to focus  
 
their efforts on the major manufactured  
 
goods within the ARRV project. The  
 
terms and conditions of the award still
 
require UAF to Buy American to the
 
extent practicable for items less than
 
$10,000. Therefore, a limited project-  
 
specific de minimis exemption for any
 
such incidental item costing $10,000 or
 
less used in and incorporated into the
 
ARRV project is justified in the public
 
interest. The Department of Energy has
 
issued a similar type of de minimis
 
exemption, relating to its Office of
 
Energy Efficiency and Renewable
 
Energy [75 FR 35447 (June 22, 2010)].
At this phase in the ARRV project, it is estimated that only $750,000 of
 
incidental items will require use of the
 
de minimis exemption. To ensure
 
proper oversight with regard to use of
 
this exemption within the project, the
 
agency hereby establishes an allowable
 
ceiling of $1.5M for the application of
 
this de minimis exemption; this
 
represents approximately 2.5% of the
 
total value of materials used in the
 
vessel. (Since the previously-granted
 
exemptions for the purchase of ARRV
 
equipment were not granted on this de
 
minimis basis, but instead because there
 
was not a domestic manufacturer of the qualifying equipment, those purchases
 
do not fall within the $1.5M ceiling for
 
the use of this de minimis exemption.)
Issuance of this limited project-specific exemption recognizes NSF's
 
commitment to expeditious spending of
 
Recovery Act dollars balanced against
 
the need for efficient implementation of
 
the Recovery Act provision while still
 
maintaining the Buy American
 
requirements for manufactured goods
 
that are greater than the de minimis
 
amount of $10,000.
III. Exemption On July 6, 2011, and under the authority of section 1605(b)(1) of the Public Law 111-5 and delegation order
 
dated 27 May 2010, with respect to the
 
Alaska Region Research Vessel Project
 
funded by NSF, the NSF Chief Financial
 
Officer granted a limited project
 
exemption for any incidental item costing $10,000 or less used in and
 
incorporated into the project. With this
 
exemption, the agency hereby
 
establishes a $1.5M ceiling for the total
 
allowable value of de minimis
 
exemptions used on this project.
Dated: July 7, 2011.
Lawrence Rudolph, General Counsel.
[FR Doc. 2011-18643 Filed 7-25-11; 8:45 am]
BILLING CODE 7555-01-P NUCLEAR REGULATORY COMMISSION
[NRC-2011-0167]
[NRC-2011-0167]
Biweekly Notice; Applications and  
terms and conditions of the award still
 
* Fax comments to: RADB at 301-require UAF to Buy American to the                      Biweekly Notice; Applications and                     492-3446.
Amendments to Facility Operating  
extent practicable for items less than                  Amendments to Facility Operating                       You can access publicly available
 
                                              $10,000. Therefore, a limited project-                  Licenses Involving No Significant                     documents related to this notice using specific de minimis exemption for any                    Hazards Considerations                               the following methods:
Licenses Involving No Significant  
such incidental item costing $10,000 or
 
* NRCs Public Document Room less used in and incorporated into the                  Background                                            (PDR): The public may examine and ARRV project is justified in the public                                                                        have copied, for a fee, publicly available Pursuant to Section 189a. (2) of the interest. The Department of Energy has                                                                        documents at the NRCs PDR, Room O1-Atomic Energy Act of 1954, as amended issued a similar type of de minimis                                                                            F21, One White Flint North, 11555 (the Act), the U.S. Nuclear Regulatory exemption, relating to its Office of                                                                          Rockville Pike, Rockville, Maryland Commission (the Commission or NRC)
Hazards Considerations Background Pursuant to Section 189a. (2) of the Atomic Energy Act of 1954, as amended (the Act), the U.S. Nuclear Regulatory
Energy Efficiency and Renewable                                                                                20852.
 
is publishing this regular biweekly
Commission (the Commission or NRC)
* NRCs Agencywide Documents Energy [75 FR 35447 (June 22, 2010)].                    notice. The Act requires the At this phase in the ARRV project, it                                                                      Access and Management System Commission publish notice of any                      (ADAMS): Publicly available documents is estimated that only $750,000 of                      amendments issued, or proposed to be incidental items will require use of the                                                                       created or received at the NRC are issued and grants the Commission the                  accessible electronically through de minimis exemption. To ensure                          authority to issue and make proper oversight with regard to use of                                                                         ADAMS in the NRC Library at http://
 
immediately effective any amendment                  www.nrc.gov/reading-rm/adams.html.
is publishing this regular biweekly
this exemption within the project, the                  to an operating license upon a agency hereby establishes an allowable                                                                        From this page, the public can gain determination by the Commission that                  entry into ADAMS, which provides text ceiling of $1.5M for the application of such amendment involves no significant                and image files of the NRCs public this de minimis exemption; this hazards consideration, notwithstanding                documents. If you do not have access to represents approximately 2.5% of the the pendency before the Commission of                 ADAMS or if there are problems in total value of materials used in the a request for a hearing from any person.             accessing the documents located in vessel. (Since the previously-granted This biweekly notice includes all                  ADAMS, contact the NRCs PDR exemptions for the purchase of ARRV notices of amendments issued, or                      reference staff at 1-800-397-4209, 301-equipment were not granted on this de proposed to be issued from June 30,                  415-4737, or by e-mail to minimis basis, but instead because there 2011 to July 13, 2011. The last biweekly              pdr.resource@nrc.gov.
 
was not a domestic manufacturer of the notice was published on July 12, 2011
notice. The Act requires the  
* Federal Rulemaking Web site:
 
qualifying equipment, those purchases (76 FR 40937).                                        Public comments and supporting do not fall within the $1.5M ceiling for the use of this de minimis exemption.)                  ADDRESSES: Please include Docket ID                  materials related to this notice can be Issuance of this limited project-                    NRC-2011-0167 in the subject line of                 found at http://www.regulations.gov by specific exemption recognizes NSFs                      your comments. Comments submitted in                  searching on Docket ID: NRC-2011-commitment to expeditious spending of                    writing or in electronic form will be                0167.
Commission publish notice of any
Recovery Act dollars balanced against                    posted on the NRC Web site and on the Federal rulemaking Web site http://                  Notice of Consideration of Issuance of the need for efficient implementation of www.regulations.gov. Because your                    Amendments to Facility Operating the Recovery Act provision while still comments will not be edited to remove                Licenses, Proposed No Significant maintaining the Buy American any identifying or contact information,               Hazards Consideration Determination, requirements for manufactured goods the NRC cautions you against including                and Opportunity for a Hearing that are greater than the de minimis amount of $10,000.                                       any information in your submission that                The Commission has made a you do not want to be publicly                        proposed determination that the III. Exemption                                          disclosed.                                           following amendment requests involve On July 6, 2011, and under the                           The NRC requests that any party                    no significant hazards consideration.
 
sroberts on DSK5SPTVN1PROD with NOTICES authority of section 1605(b)(1) of the                  soliciting or aggregating comments                    Under the Commissions regulations in Public Law 111-5 and delegation order                    received from other persons for                       Title 10 of the Code of Federal dated 27 May 2010, with respect to the                  submission to the NRC inform those                    Regulations (10 CFR), 50.92, this means Alaska Region Research Vessel Project                    persons that the NRC will not edit their              that operation of the facility in funded by NSF, the NSF Chief Financial                  comments to remove any identifying or                accordance with the proposed Officer granted a limited project                        contact information, and therefore, they              amendment would not (1) Involve a exemption for any incidental item                        should not include any information in                significant increase in the probability or VerDate Mar<15>2010  16:12 Jul 25, 2011  Jkt 223001  PO 00000  Frm 00045  Fmt 4703  Sfmt 4703  E:\FR\FM\26JYN1.SGM  26JYN1
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 June 30, 2011 to July 13, 2011. The last biweekly
 
notice was published on July 12, 2011
 
(76 FR 40937).
ADDRESSES: Please include Docket ID NRC-2011-0167 in the subject line of  
 
your comments. Comments submitted in  
 
writing or in electronic form will be
 
posted on the NRC Web site and on the
 
Federal rulemaking Web site http://
www.regulations.gov.
Because your comments will not be edited to remove
 
any identifying or contact information, the NRC cautions you against including
 
any information in your submission that
 
you do not want to be publicly
 
disclosed.
The NRC requests that any party soliciting or aggregating comments
 
received from other persons for
 
submission to the NRC inform those  
 
persons that the NRC will not edit their
 
comments to remove any identifying or
 
contact information, and therefore, they
 
should not include any information in their comments that they do not want
 
publicly disclosed.
You may submit comments by any one of the following methods.
*Federal Rulemaking Web site:
Go to http://www.regulations.gov and search for documents filed under Docket ID  
 
NRC-NRC-2011-0167. Address
 
questions about NRC dockets to Carol
 
Gallagher 301-492-3668; e-mail
 
Carol.Gallagher@nrc.gov.  
*Mail comments to:
Chief, Rules, Announcements, and Directives Branch (RADB), Office of Administration, Mail
 
Stop: TWB-05-B01M, U.S. Nuclear
 
Regulatory Commission, Washington, DC 20555-0001.
*Fax comments to:
RADB at 301-492-3446.
You can access publicly available documents related to this notice using
 
the following methods:
*NRC's Public Document Room (PDR): The public may examine and have copied, for a fee, publicly available
 
documents at the NRC's PDR, Room O1-
 
F21, One White Flint North, 11555
 
Rockville Pike, Rockville, Maryland
 
20852. *NRC's Agencywide Documents Access and Management System (ADAMS): Publicly available documents created or received at the NRC are
 
accessible electronically through
 
ADAMS in the NRC Library at http://
www.nrc.gov/reading-rm/adams.html.
 
From this page, the public can gain
 
entry into ADAMS, which provides text
 
and image files of the NRC's public
 
documents. If you do not have access to
 
ADAMS or if there are problems in
 
accessing the documents located in
 
ADAMS, contact the NRC's PDR
 
reference staff at 1-800-397-4209, 301-
 
415-4737, or by e-mail to
 
pdr.resource@nrc.gov.
*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-
 
0167. Notice of Consideration of Issuance of Amendments to Facility Operating
 
Licenses, Proposed No Significant
 
Hazards Consideration Determination, and Opportunity for a Hearing The Commission has made a proposed determination that the
 
following amendment requests involve
 
no significant hazards consideration.
 
Under the Commission's regulations in
 
Title 10 of the Code of Federal
 
Regulations (10 CFR), 50.92, this means
 
that operation of the facility in
 
accordance with the proposed
 
amendment would not (1) Involve a
 
significant increase in the probability or VerDate Mar<15>2010 16:12 Jul 25, 2011Jkt 223001PO 00000Frm 00045Fmt 4703Sfmt 4703E:\FR\FM\26JYN1.SGM26JYN1 sroberts on DSK5SPTVN1PROD with NOTICES 44615 Federal Register/Vol. 76, No. 143/Tuesday, July 26, 2011/Notices consequences of an accident previously evaluated; or (2) create the possibility of
 
a new or different kind of accident from
 
any accident previously evaluated; or
 
(3) involve a significant reduction in a
 
margin of safety. The basis for this
 
proposed determination for each
 
amendment request is shown below.
The Commission is seeking public comments on this proposed
 
determination. Any comments received
 
within 30 days after the date of
 
publication of this notice will be
 
considered in making any final
 
determination.
Normally, the Commission will not issue the amendment until the
 
expiration of 60 days after the date of
 
publication of this notice. The
 
Commission may issue the license
 
amendment before expiration of the 60-
 
day period provided that its final
 
determination is that the amendment
 
involves no significant hazards
 
consideration. In addition, the
 
Commission may issue the amendment
 
prior to the expiration of the 30-day
 
comment period should circumstances
 
change during the 30-day comment
 
period such that failure to act in a
 
timely way would result, for example in
 
derating or shutdown of the facility.
 
Should the Commission take action
 
prior to the expiration of either the
 
comment period or the notice period, it
 
will publish in the Federal Register a
notice of issuance. Should the
 
Commission make a final No Significant
 
Hazards Consideration Determination, any hearing will take place after
 
issuance. The Commission expects that
 
the need to take this action will occur
 
very infrequently.
Within 60 days after the date of publication of this notice, any person(s)
 
whose interest may be affected by this
 
action may file a request for a hearing
 
and a petition to intervene with respect
 
to issuance of the amendment to the
 
subject facility operating license.
 
Requests for a hearing and a petition for
 
leave to intervene shall be filed in
 
accordance with the Commission's
 
''Rules of Practice for Domestic
 
Licensing Proceedings'' in 10 CFR part
: 2. Interested person(s) should consult a
 
current copy of 10 CFR 2.309, which is
 
available at the NRC's PDR, located at
 
One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852. NRC
 
regulations are accessible electronically
 
from the NRC Library on the NRC Web
 
site at http://www.nrc.gov/reading-rm/
 
doc-collections/cfr/.
If a request for a hearing or petition for leave to intervene
 
is filed by the above date, the
 
Commission or a presiding officer
 
designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board
 
Panel, will rule on the request and/or
 
petition; and the Secretary or the Chief
 
Administrative Judge of the Atomic
 
Safety and Licensing Board will issue a
 
notice of a hearing or an appropriate
 
order. As required by 10 CFR 2.309, a petition for leave to intervene shall set
 
forth with particularity the interest of
 
the petitioner in the proceeding, and
 
how that interest may be affected by the
 
results of the proceeding. The petition
 
should specifically explain the reasons
 
why intervention should be permitted
 
with particular reference to the
 
following general requirements: (1) The
 
name, address, and telephone number of
 
the requestor or petitioner; (2) the
 
nature of the requestor's/petitioner's
 
right under the Act to be made a party
 
to the proceeding; (3) the nature and
 
extent of the requestor's/petitioner's
 
property, financial, or other interest in
 
the proceeding; and (4) the possible
 
effect of any decision or order which
 
may be entered in the proceeding on the
 
requestor's/petitioner's interest. The
 
petition must also identify the specific
 
contentions which the requestor/
 
petitioner seeks to have litigated at the
 
proceeding.
Each contention must consist of a specific statement of the issue of law or
 
fact to be raised or controverted. In
 
addition, the requestor/petitioner shall
 
provide a brief explanation of the bases
 
for the contention and a concise
 
statement of the alleged facts or expert
 
opinion which support the contention
 
and on which the requestor/petitioner
 
intends to rely in proving the contention
 
at the hearing. The requestor/petitioner
 
must also provide references to those
 
specific sources and documents of
 
which the petitioner is aware and on
 
which the requestor/petitioner intends
 
to rely to establish those facts or expert
 
opinion. The petition must include
 
sufficient information to show that a
 
genuine dispute exists with the
 
applicant on a material issue of law or
 
fact. Contentions shall be limited to
 
matters within the scope of the
 
amendment under consideration. The
 
contention must be one which, if
 
proven, would entitle the requestor/
 
petitioner to relief. A requestor/
petitioner who fails to satisfy these
 
requirements with respect to at least one
 
contention will not be permitted to
 
participate as a party.
Those permitted to intervene become parties to the proceeding, subject to any
 
limitations in the order granting leave to
 
intervene, and have the opportunity to
 
participate fully in the conduct of the
 
hearing. If a hearing is requested, the Commission will make a final determination on the issue of no
 
significant hazards consideration. The
 
final determination will serve to decide
 
when the hearing is held. If the final
 
determination is that the amendment
 
request involves no significant hazards
 
consideration, the Commission may
 
issue the amendment and make it
 
immediately effective, notwithstanding
 
the request for a hearing. Any hearing
 
held would take place after issuance of
 
the amendment. If the final
 
determination is that the amendment
 
request involves a significant hazards
 
consideration, then any hearing held
 
would take place before the issuance of
 
any amendment.
All documents filed in NRC adjudicatory proceedings, including a
 
request for hearing, a petition for leave
 
to intervene, any motion or other
 
document filed in the proceeding prior
 
to the submission of a request for
 
hearing or petition to intervene, and
 
documents filed by interested
 
governmental entities participating
 
under 10 CFR 2.315(c), must be filed in
 
accordance with the NRC E-Filing rule
 
(72 FR 49139, August 28, 2007). The E-
 
Filing process requires participants to
 
submit and serve all adjudicatory
 
documents over the internet, or in some
 
cases to mail copies on electronic
 
storage media. Participants may not
 
submit paper copies of their filings
 
unless they seek an exemption in
 
accordance with the procedures
 
described below.
To comply with the procedural requirements of E-Filing, at least 10
 
days prior to the filing deadline, the
 
participant should contact the Office of
 
the Secretary by e-mail at
 
hearing.docket@nrc.gov, or by telephone at 301-415-1677, to request (1) a digital
 
identification (ID) certificate, which
 
allows the participant (or its counsel or
 
representative) to digitally sign
 
documents and access the E-Submittal
 
server for any proceeding in which it is
 
participating; and (2) advise the
 
Secretary that the participant will be
 
submitting a request or petition for
 
hearing (even in instances in which the
 
participant, or its counsel or
 
representative, already holds an NRC-
 
issued digital ID certificate). Based upon this information, the Secretary will
 
establish an electronic docket for the
 
hearing in this proceeding if the
 
Secretary has not already established an
 
electronic docket.
Information about applying for a digital ID certificate is available on
 
NRC's public Web site at http://
www.nrc.gov/site-help/e-submittals/
 
apply-certificates.html.
System VerDate Mar<15>2010 16:12 Jul 25, 2011Jkt 223001PO 00000Frm 00046Fmt 4703Sfmt 4703E:\FR\FM\26JYN1.SGM26JYN1 sroberts on DSK5SPTVN1PROD with NOTICES 44616 Federal Register/Vol. 76, No. 143/Tuesday, July 26, 2011/Notices 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 MSHD.Resource@nrc.gov, or by a toll-free call at 1-866-672-7640. The NRC
 
Meta System Help Desk is available
 
between 8 a.m. and 8 p.m., Eastern
 
Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not submitting
 
documents electronically must file an
 
exemption request, in accordance with
 
10 CFR 2.302(g), with their initial paper
 
filing requesting authorization to
 
continue to submit documents in paper
 
format. Such filings must be submitted
 
by: (1) first class mail addressed to the
 
Office of the Secretary of the
 
Commission, U.S. Nuclear Regulatory
 
Commission, Washington, DC 20555-
 
0001, Attention: Rulemaking and
 
Adjudications Staff; or (2) courier, express mail, or expedited delivery
 
service to the Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking
 
and Adjudications Staff. Participants
 
filing a document in this manner are
 
responsible for serving the document on
 
all other participants. Filing is
 
considered complete by first-class mail
 
as of the time of deposit in the mail, or
 
by courier, express mail, or expedited
 
delivery service upon depositing the
 
document with the provider of the
 
service. A presiding officer, having
 
granted an exemption request from
 
using E-Filing, may require a participant
 
or party to use E-Filing if the presiding
 
officer subsequently determines that the
 
reason for granting the exemption from
 
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in NRC's
 
electronic hearing docket which is
 
available to the public at http://
ehd1.nrc.gov/EHD/, unless excluded pursuant to an order of the Commission, or the presiding officer. Participants are
 
requested not to include personal
 
privacy information, such as social
 
security numbers, home addresses, or
 
home phone numbers in their filings, unless an NRC regulation or other law
 
requires submission of such
 
information. With respect to copyrighted works, except for limited
 
excerpts that serve the purpose of the
 
adjudicatory filings and would
 
constitute a Fair Use application, participants are requested not to include
 
copyrighted materials in their
 
submission.
Petitions for leave to intervene must be filed no later than 60 days from the
 
date of publication of this notice. Non-timely filings will not be entertained
 
absent a determination by the presiding
 
officer that the petition or request
 
should be granted or the contentions
 
should be admitted, based on a
 
balancing of the factors specified in 10
 
CFR 2.309(c)(1)(i)-(viii).
For further details with respect to this license amendment application, see the
 
application for amendment which is
 
available for public inspection at the
 
NRC's PDR, located at One White Flint
 
North, Room O1-F21, 11555 Rockville
 
Pike (first floor), Rockville, Maryland
 
20852. Publicly available documents
 
created or received at the NRC are
 
accessible electronically through
 
ADAMS in the NRC Library at http://
www.nrc.gov/reading-rm/adams.html.
 
Persons who do not have access to
 
ADAMS or who encounter problems in
 
accessing the documents located in
 
ADAMS, should contact the NRC PDR
 
Reference staff at 1-800-397-4209, 301-
 
415-4737, or by e-mail to
 
pdr.resource@nrc.gov.
Entergy Gulf States Louisiana, LLC, and Entergy Operations, Inc., Docket No.
 
50-458, River Bend Station, Unit 1, West Feliciana Parish, Louisiana Date of amendment request:
June 10, 2011. Description of amendment request:
The proposed amendment would revise
 
the Technical Specifications (TSs) to
 
add a new limiting condition for
 
operation (LCO) Applicability
 
requirement, LCO 3.0.9, and its
 
associated Bases, relating to the
 
modification of requirements regarding
 
the impact of unavailable barriers, not
 
explicitly addressed in TSs, but
 
required for operability of supported
 
systems in TSs. This change is
 
consistent with NRC-approved
 
Technical Specification Task Force (TSTF) Improved Standard Technical
 
Specification Change Traveler, TSTF-
 
427, Revision 2, ''Allowance for Non
 
Technical Specification Barrier
 
Degradation on Supported System
 
OPERABILITY.''
The NRC staff issued a Notice of Opportunity to Comment in the Federal Register on June 2, 2006 (71 FR 32145), on possible amendments to revise the
 
plant-specific TSs, including a model
 
safety evaluation and model no
 
significant hazards consideration
 
determination using the consolidated
 
line item improvement process. The
 
NRC staff subsequently issued a Notice
 
of Availability of this TS improvement
 
in the Federal Register on October 3, 2006 (71 FR 58444). The licensee
 
affirmed the applicability of the model
 
no significant hazards consideration VerDate Mar<15>2010 16:12 Jul 25, 2011Jkt 223001PO 00000Frm 00047Fmt 4703Sfmt 4703E:\FR\FM\26JYN1.SGM26JYN1 sroberts on DSK5SPTVN1PROD with NOTICES 44617 Federal Register/Vol. 76, No. 143/Tuesday, July 26, 2011/Notices determination in its application dated June 10, 2011.
Basis for proposed no significant hazards consideration determination:
 
As required by 10 CFR 50.91(a), an


analysis of the issue of no significant  
Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices                                          44615 consequences of an accident previously                  Chief Administrative Judge of the                        If a hearing is requested, the evaluated; or (2) create the possibility of              Atomic Safety and Licensing Board                    Commission will make a final a new or different kind of accident from                Panel, will rule on the request and/or                determination on the issue of no any accident previously evaluated; or                    petition; and the Secretary or the Chief              significant hazards consideration. The (3) involve a significant reduction in a                Administrative Judge of the Atomic                    final determination will serve to decide margin of safety. The basis for this                    Safety and Licensing Board will issue a              when the hearing is held. If the final proposed determination for each                          notice of a hearing or an appropriate                determination is that the amendment amendment request is shown below.                        order.                                                request involves no significant hazards The Commission is seeking public                        As required by 10 CFR 2.309, a                    consideration, the Commission may comments on this proposed                                petition for leave to intervene shall set            issue the amendment and make it determination. Any comments received                    forth with particularity the interest of              immediately effective, notwithstanding within 30 days after the date of                        the petitioner in the proceeding, and                the request for a hearing. Any hearing publication of this notice will be                      how that interest may be affected by the              held would take place after issuance of considered in making any final                          results of the proceeding. The petition              the amendment. If the final determination.                                          should specifically explain the reasons              determination is that the amendment Normally, the Commission will not                    why intervention should be permitted                  request involves a significant hazards issue the amendment until the                            with particular reference to the                      consideration, then any hearing held expiration of 60 days after the date of                  following general requirements: (1) The              would take place before the issuance of publication of this notice. The                          name, address, and telephone number of                any amendment.
Commission may issue the license                        the requestor or petitioner; (2) the                    All documents filed in NRC amendment before expiration of the 60-                  nature of the requestors/petitioners                adjudicatory proceedings, including a day period provided that its final                      right under the Act to be made a party                request for hearing, a petition for leave determination is that the amendment                      to the proceeding; (3) the nature and                to intervene, any motion or other involves no significant hazards                          extent of the requestors/petitioners                document filed in the proceeding prior consideration. In addition, the                          property, financial, or other interest in            to the submission of a request for Commission may issue the amendment                      the proceeding; and (4) the possible                  hearing or petition to intervene, and prior to the expiration of the 30-day                    effect of any decision or order which                documents filed by interested comment period should circumstances                      may be entered in the proceeding on the              governmental entities participating change during the 30-day comment                        requestors/petitioners interest. The                under 10 CFR 2.315(c), must be filed in period such that failure to act in a                    petition must also identify the specific              accordance with the NRC E-Filing rule timely way would result, for example in                  contentions which the requestor/                      (72 FR 49139, August 28, 2007). The E-derating or shutdown of the facility.                    petitioner seeks to have litigated at the            Filing process requires participants to Should the Commission take action                        proceeding.                                          submit and serve all adjudicatory prior to the expiration of either the                      Each contention must consist of a                  documents over the internet, or in some comment period or the notice period, it                  specific statement of the issue of law or            cases to mail copies on electronic will publish in the Federal Register a                  fact to be raised or controverted. In                storage media. Participants may not notice of issuance. Should the                          addition, the requestor/petitioner shall              submit paper copies of their filings Commission make a final No Significant                  provide a brief explanation of the bases              unless they seek an exemption in Hazards Consideration Determination,                    for the contention and a concise                      accordance with the procedures any hearing will take place after                        statement of the alleged facts or expert              described below.
issuance. The Commission expects that                    opinion which support the contention                    To comply with the procedural the need to take this action will occur                  and on which the requestor/petitioner                requirements of E-Filing, at least 10 very infrequently.                                      intends to rely in proving the contention            days prior to the filing deadline, the Within 60 days after the date of                      at the hearing. The requestor/petitioner              participant should contact the Office of publication of this notice, any person(s)                must also provide references to those                the Secretary by e-mail at whose interest may be affected by this                  specific sources and documents of                    hearing.docket@nrc.gov, or by telephone action may file a request for a hearing                  which the petitioner is aware and on                  at 301-415-1677, to request (1) a digital and a petition to intervene with respect                which the requestor/petitioner intends                identification (ID) certificate, which to issuance of the amendment to the                      to rely to establish those facts or expert            allows the participant (or its counsel or subject facility operating license.                      opinion. The petition must include                    representative) to digitally sign Requests for a hearing and a petition for                sufficient information to show that a                documents and access the E-Submittal leave to intervene shall be filed in                    genuine dispute exists with the                      server for any proceeding in which it is accordance with the Commissions                        applicant on a material issue of law or              participating; and (2) advise the Rules of Practice for Domestic                        fact. Contentions shall be limited to                Secretary that the participant will be Licensing Proceedings in 10 CFR part                  matters within the scope of the                      submitting a request or petition for
: 2. Interested person(s) should consult a                amendment under consideration. The                    hearing (even in instances in which the current copy of 10 CFR 2.309, which is                  contention must be one which, if                      participant, or its counsel or available at the NRCs PDR, located at                  proven, would entitle the requestor/                  representative, already holds an NRC-One White Flint North, Room O1-F21,                      petitioner to relief. A requestor/                    issued digital ID certificate). Based upon 11555 Rockville Pike (first floor),                      petitioner who fails to satisfy these                this information, the Secretary will Rockville, Maryland 20852. NRC                          requirements with respect to at least one            establish an electronic docket for the regulations are accessible electronically                contention will not be permitted to                  hearing in this proceeding if the sroberts on DSK5SPTVN1PROD with NOTICES from the NRC Library on the NRC Web                      participate as a party.                              Secretary has not already established an site at http://www.nrc.gov/reading-rm/                      Those permitted to intervene become                electronic docket.
doc-collections/cfr/. If a request for a                parties to the proceeding, subject to any                Information about applying for a hearing or petition for leave to intervene              limitations in the order granting leave to            digital ID certificate is available on is filed by the above date, the                          intervene, and have the opportunity to                NRCs public Web site at http://
Commission or a presiding officer                        participate fully in the conduct of the              www.nrc.gov/site-help/e-submittals/
designated by the Commission or by the                  hearing.                                              apply-certificates.html. System VerDate Mar<15>2010  16:12 Jul 25, 2011  Jkt 223001  PO 00000  Frm 00046  Fmt 4703  Sfmt 4703  E:\FR\FM\26JYN1.SGM  26JYN1


hazards consideration is presented
44616                          Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices requirements for accessing the E-                        Desk through the Contact Us link                  timely filings will not be entertained Submittal server are detailed in NRCs                  located on the NRC Web site at http://                absent a determination by the presiding Guidance for Electronic Submission,                  www.nrc.gov/site-help/e-                              officer that the petition or request which is available on the agencys                      submittals.html, by e-mail at                        should be granted or the contentions public Web site at http://www.nrc.gov/                  MSHD.Resource@nrc.gov, or by a toll-                  should be admitted, based on a site-help/e-submittals.html. Participants                free call at 1-866-672-7640. The NRC                  balancing of the factors specified in 10 may attempt to use other software not                    Meta System Help Desk is available                    CFR 2.309(c)(1)(i)-(viii).
 
listed on the Web site, but should note                  between 8 a.m. and 8 p.m., Eastern                      For further details with respect to this that the NRCs E-Filing system does not                  Time, Monday through Friday,                          license amendment application, see the support unlisted software, and the NRC                  excluding government holidays.                        application for amendment which is Meta System Help Desk will not be able                      Participants who believe that they                available for public inspection at the to offer assistance in using unlisted                    have a good cause for not submitting                  NRCs PDR, located at One White Flint software.                                                documents electronically must file an                 North, Room O1-F21, 11555 Rockville If a participant is electronically                    exemption request, in accordance with                Pike (first floor), Rockville, Maryland submitting a document to the NRC in                      10 CFR 2.302(g), with their initial paper            20852. Publicly available documents accordance with the E-Filing rule, the                  filing requesting authorization to                    created or received at the NRC are participant must file the document                      continue to submit documents in paper                accessible electronically through using the NRCs online, Web-based                        format. Such filings must be submitted                ADAMS in the NRC Library at http://
below: Criterion 1-The Proposed Change Does Not Involve a Significant Increase in the  
submission form. In order to serve                      by: (1) first class mail addressed to the            www.nrc.gov/reading-rm/adams.html.
 
documents through the Electronic                        Office of the Secretary of the                        Persons who do not have access to Information Exchange System, users                      Commission, U.S. Nuclear Regulatory                  ADAMS or who encounter problems in will be required to install a Web                        Commission, Washington, DC 20555-                    accessing the documents located in browser plug-in from the NRC Web site.                  0001, Attention: Rulemaking and                       ADAMS, should contact the NRC PDR Further information on the Web-based                    Adjudications Staff; or (2) courier,                  Reference staff at 1-800-397-4209, 301-submission form, including the                          express mail, or expedited delivery                  415-4737, or by e-mail to installation of the Web browser plug-in,                service to the Office of the Secretary,              pdr.resource@nrc.gov.
Probability or Consequences of an
is available on the NRCs public Web                    Sixteenth Floor, One White Flint North, site at http://www.nrc.gov/site-help/e-                  11555 Rockville Pike, Rockville,                      Entergy Gulf States Louisiana, LLC, and submittals.html.                                        Maryland 20852, Attention: Rulemaking                Entergy Operations, Inc., Docket No.
 
Once a participant has obtained a                    and Adjudications Staff. Participants                50-458, River Bend Station, Unit 1, digital ID certificate and a docket has                  filing a document in this manner are                  West Feliciana Parish, Louisiana been created, the participant can then                  responsible for serving the document on                  Date of amendment request: June 10, submit a request for hearing or petition                all other participants. Filing is                    2011.
Accident Previously Evaluated The proposed change allows a delay time for entering a supported system  
for leave to intervene. Submissions                      considered complete by first-class mail should be in Portable Document Format                                                                            Description of amendment request:
 
as of the time of deposit in the mail, or (PDF) in accordance with NRC guidance                                                                          The proposed amendment would revise by courier, express mail, or expedited available on the NRC public Web site at                 delivery service upon depositing the                  the Technical Specifications (TSs) to http://www.nrc.gov/site-help/e-                          document with the provider of the                    add a new limiting condition for submittals.html. A filing is considered                  service. A presiding officer, having                  operation (LCO) Applicability complete at the time the documents are                  granted an exemption request from                    requirement, LCO 3.0.9, and its submitted through the NRCs E-Filing                    using E-Filing, may require a participant            associated Bases, relating to the system. To be timely, an electronic                      or party to use E-Filing if the presiding            modification of requirements regarding filing must be submitted to the E-Filing                officer subsequently determines that the              the impact of unavailable barriers, not system no later than 11:59 p.m. Eastern                  reason for granting the exemption from                explicitly addressed in TSs, but Time on the due date. Upon receipt of                    use of E-Filing no longer exists.                    required for operability of supported a transmission, the E-Filing system                        Documents submitted in adjudicatory                systems in TSs. This change is time-stamps the document and sends                      proceedings will appear in NRCs                      consistent with NRC-approved the submitter an e-mail notice                          electronic hearing docket which is                    Technical Specification Task Force confirming receipt of the document. The                  available to the public at http://                    (TSTF) Improved Standard Technical E-Filing system also distributes an e-                  ehd1.nrc.gov/EHD/, unless excluded                    Specification Change Traveler, TSTF-mail notice that provides access to the                  pursuant to an order of the Commission,              427, Revision 2, Allowance for Non document to the NRC Office of the                        or the presiding officer. Participants are           Technical Specification Barrier General Counsel and any others who                      requested not to include personal                    Degradation on Supported System have advised the Office of the Secretary                privacy information, such as social                  OPERABILITY.
technical specification (TS) when the  
that they wish to participate in the                    security numbers, home addresses, or                    The NRC staff issued a Notice of proceeding, so that the filer need not                  home phone numbers in their filings,                  Opportunity to Comment in the Federal serve the documents on those                            unless an NRC regulation or other law                Register on June 2, 2006 (71 FR 32145),
 
participants separately. Therefore,                      requires submission of such                          on possible amendments to revise the applicants and other participants (or                    information. With respect to                          plant-specific TSs, including a model their counsel or representative) must                    copyrighted works, except for limited                safety evaluation and model no apply for and receive a digital ID                      excerpts that serve the purpose of the                significant hazards consideration certificate before a hearing request/                    adjudicatory filings and would                        determination using the consolidated sroberts on DSK5SPTVN1PROD with NOTICES petition to intervene is filed so that they              constitute a Fair Use application,                   line item improvement process. The can obtain access to the document via                    participants are requested not to include            NRC staff subsequently issued a Notice the E-Filing system.                                    copyrighted materials in their                        of Availability of this TS improvement A person filing electronically using                  submission.                                          in the Federal Register on October 3, the agencys adjudicatory E-Filing                          Petitions for leave to intervene must              2006 (71 FR 58444). The licensee system may seek assistance by                            be filed no later than 60 days from the              affirmed the applicability of the model contacting the NRC Meta System Help                      date of publication of this notice. Non-              no significant hazards consideration VerDate Mar<15>2010  16:12 Jul 25, 2011  Jkt 223001  PO 00000  Frm 00047  Fmt 4703  Sfmt 4703  E:\FR\FM\26JYN1.SGM  26JYN1
inoperability is due solely to an  
 
unavailable barrier if risk is assessed
 
and managed. The postulated initiating
 
events which may require a functional
 
barrier are limited to those with low
 
frequencies of occurrence, and the  
 
overall TS system safety function would
 
still be available for the majority of
 
anticipated challenges. Therefore, the  
 
probability of an accident previously
 
evaluated is not significantly increased, if at all. The consequences of an  
 
accident while relying on the allowance
 
provided by proposed LCO 3.0.9 are no  
 
different than the consequences of an
 
accident while relying on the TS
 
required actions in effect without the  
 
allowance provided by proposed LCO
 
3.0.9. Therefore, the consequences of an
 
accident previously evaluated are not  
 
significantly affected by this change.
The addition of a requirement to assess
 
and manage the risk introduced by this
 
change will further minimize possible  
 
concerns. Therefore, this change does
 
not involve a significant increase in the  
 
probability or consequences of an


Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices                                                44617 determination in its application dated                  Criterion 3The Proposed Change Does                  maintenance and issuance of updates to June 10, 2011.                                          Not Involve a Significant Reduction in                the TOCs will transfer from the U.S.
Basis for proposed no significant                      the Margin of Safety                                  Nuclear Regulatory Commission (NRC) hazards consideration determination:                                                                          to the licensee. The TOCs will no longer The proposed change allows a delay As required by 10 CFR 50.91(a), an                                                                            be included in the TSs and, as such, time for entering a supported system TS analysis of the issue of no significant                                                                        will no longer be part of Appendix A to when the inoperability is due solely to hazards consideration is presented                                                                            the Operating License.
an unavailable barrier, if risk is assessed below:                                                                                                            Basis for proposed no significant and managed. The postulated initiating Criterion 1The Proposed Change Does                                                                          hazards consideration determination:
events which may require a functional Not Involve a Significant Increase in the                                                                      As required by 10 CFR 50.91(a), the barrier are limited to those with low Probability or Consequences of an                                                                              licensee has provided its analysis of the frequencies of occurrence, and the Accident Previously Evaluated                                                                                  issue of no significant hazards overall TS system safety function would consideration, which is presented The proposed change allows a delay                    still be available for the majority of below:
time for entering a supported system                    anticipated challenges. The risk impact technical specification (TS) when the                    of the proposed TS changes was                          1. Does the proposed amendment involve assessed following the three-tiered                  a significant increase in the probability or inoperability is due solely to an                                                                              consequences of an accident previously unavailable barrier if risk is assessed                  approach recommended in [NRC evaluated?
and managed. The postulated initiating                  Regulatory Guide (RG) 1.177, An                        Response: No.
events which may require a functional                    Approach for Plant-Specific, Risk-                      The proposed amendment is barrier are limited to those with low                    Informed Decisionmaking: Technical                    administrative and affects control of a frequencies of occurrence, and the                      Specifications]. A bounding risk                    document, the TOCs, listing the overall TS system safety function would                  assessment was performed to justify the              specifications in the plant TSs. Transferring still be available for the majority of                  proposed TS changes. This application                control from the NRC to NextEra does not of LCO 3.0.9 is predicated upon the                  affect the operation, physical configuration, anticipated challenges. Therefore, the licensees performance of a risk                      or function of plant equipment or systems.
probability of an accident previously                                                                          The proposed amendment does not impact evaluated is not significantly increased,                assessment and the management of                      the initiators or assumptions of analyzed if at all. The consequences of an                        plant risk. The net change to the margin              events, nor does it impact the mitigation of accident while relying on the allowance                  of safety is insignificant as indicated by            accidents or transient events.
provided by proposed LCO 3.0.9 are no                    the anticipated low levels of associated                Therefore, the proposed amendment does different than the consequences of an                    risk (ICCDP [incremental conditional                  not involve a significant increase in the accident while relying on the TS                        core damage probability] and ICLERP                  probability or consequences of an accident required actions in effect without the                  [incremental conditional large early                  previously evaluated.
allowance provided by proposed LCO                      release probability]) as shown in Table                  2. Does the proposed amendment create 1 of Section 3.1.1 in the Safety                      the possibility of a new or different kind of 3.0.9. Therefore, the consequences of an accident from any accident previously accident previously evaluated are not                    Evaluation. Therefore, this change does              evaluated?
significantly affected by this change.                  not involve a significant reduction in a                Response: No.
The addition of a requirement to assess                  margin of safety.                                        The proposed amendment is and manage the risk introduced by this                      The NRC staff has reviewed the                    administrative and does not alter plant change will further minimize possible                    analysis and, based on this review, it                configuration, require installation of new concerns. Therefore, this change does                    appears that the three standards of 10                equipment, alter assumptions about not involve a significant increase in the                CFR 50.92(c) are satisfied. Therefore, the            previously analyzed accidents, or impact probability or consequences of an                        NRC staff proposes to determine that the              operation or function of plant equipment or amendment request involves no                        systems.
accident previously evaluated.
accident previously evaluated.
Criterion 2-The Proposed Change Does Not Create the Possibility of a New or
Therefore, this proposed amendment does significant hazards consideration.                   not create the possibility of a new or different Criterion 2The Proposed Change Does Attorney for licensee: Joseph A.                   kind of accident from any accident Not Create the Possibility of a New or Aluise, Associate General Council                   previously evaluated.
 
Different Kind of Accident From any Nuclear, Entergy Services, Inc., 639                     3. Does the proposed amendment involve Previously Evaluated Loyola Avenue, New Orleans, Louisiana                 a significant reduction in a margin of safety?
Different Kind of Accident From any
The proposed change does not                         70113.                                                   Response: No.
 
involve a physical alteration of the plant                  NRC Branch Chief: Michael T.                         The proposed amendment is (no new or different type of equipment                   Markley.                                             administrative. The TOCs is not required by will be installed). Allowing delay times                                                                      regulation to be in the TSs. Removal does not for entering supported system TS when                    NextEra Energy Point Beach, LLC                      impact any safety assumptions or have the inoperability is due solely to an                        (NextEra, the Licensee), Docket Nos.                  potential to reduce a margin of safety. The 50-266 and 50-301, Point Beach                        proposed amendment involves a transfer of unavailable barrier, if risk is assessed                                                                      control of the TOCs from the NRC to NextEra.
Previously Evaluated The proposed change does not involve a physical alteration of the plant (no new or different type of equipment
and managed, will not introduce new                      Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowac County,                        No change in the technical content of the TSs failure modes or effects and will not, in                                                                      is involved. Consequently, transfer from the the absence of other unrelated failures,                Wisconsin NRC to NextEra has no impact on the margin lead to an accident whose consequences                      Date of amendment request: June 23,               of safety.
 
exceed the consequences of accidents                     2011.                                                   Therefore, the proposed amendment does previously evaluated. The addition of a                     Description of amendment request:                 not involve a significant reduction in a sroberts on DSK5SPTVN1PROD with NOTICES requirement to assess and manage the                     The proposed amendment will remove                    margin of safety.
will be installed). Allowing delay times
risk introduced by this change will                      the Table of Contents from the                           The NRC staff has reviewed the further minimize possible concerns.                      Technical Specifications and place it                licensees analysis and, based on this Thus, this change does not create the                    under licensee control. The Table of                  review, it appears that the three possibility of a new or different kind of                Contents (TOCs) for the Technical                    standards of 10 CFR 50.92(c) are accident from an accident previously                    Specifications (TSs) is not being                    satisfied. Therefore, the NRC staff evaluated.                                               eliminated. The responsibility for                   proposes to determine that the VerDate Mar<15>2010   16:12 Jul 25, 2011  Jkt 223001  PO 00000  Frm 00048  Fmt 4703  Sfmt 4703  E:\FR\FM\26JYN1.SGM  26JYN1
 
for entering supported system TS when
 
inoperability is due solely to an
 
unavailable barrier, if risk is assessed
 
and managed, will not introduce new
 
failure modes or effects and will not, in
 
the absence of other unrelated failures, lead to an accident whose consequences
 
exceed the consequences of accidents
 
previously evaluated. The addition of a
 
requirement to assess and manage the
 
risk introduced by this change will
 
further minimize possible concerns.
 
Thus, this change does not create the  
 
possibility of a new or different kind of
 
accident from an accident previously
 
evaluated.
Criterion 3-The Proposed Change Does  
 
Not Involve a Significant Reduction in
 
the Margin of Safety The proposed change allows a delay time for entering a supported system TS
 
when the inoperability is due solely to
 
an unavailable barrier, if risk is assessed
 
and managed. The postulated initiating
 
events which may require a functional
 
barrier are limited to those with low
 
frequencies of occurrence, and the
 
overall TS system safety function would
 
still be available for the majority of
 
anticipated challenges. The risk impact
 
of the proposed TS changes was
 
assessed following the three-tiered
 
approach recommended in [NRC
 
Regulatory Guide (RG) 1.177, ''An
 
Approach for Plant-Specific, Risk-
 
Informed Decisionmaking: Technical
 
Specifications'']. A bounding risk
 
assessment was performed to justify the
 
proposed TS changes. This application
 
of LCO 3.0.9 is predicated upon the  
 
licensee's performance of a risk
 
assessment and the management of
 
plant risk. The net change to the margin
 
of safety is insignificant as indicated by
 
the anticipated low levels of associated
 
risk (ICCDP [incremental conditional
 
core damage probability] and ICLERP
 
[incremental conditional large early
 
release probability]) as shown in Table
 
1 of Section 3.1.1 in the Safety
 
Evaluation. Therefore, this change does
 
not involve a significant reduction in a
 
margin of safety.
The NRC staff has reviewed the 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:
Joseph A.
Aluise, Associate General Council-
 
Nuclear, Entergy Services, Inc., 639  
 
Loyola Avenue, New Orleans, Louisiana  
 
70113. NRC Branch Chief:
Michael T.
Markley. NextEra Energy Point Beach, LLC (NextEra, the Licensee), Docket Nos.
 
50-266 and 50-301, Point Beach
 
Nuclear Plant, Units 1 and 2, Town of
 
Two Creeks, Manitowac County, Wisconsin Date of amendment request:
June 23, 2011. Description of amendment request:
The proposed amendment will remove
 
the Table of Contents from the
 
Technical Specifications and place it
 
under licensee control. The Table of
 
Contents (TOCs) for the Technical
 
Specifications (TSs) is not being
 
eliminated. The responsibility for maintenance and issuance of updates to
 
the TOCs will transfer from the U.S.
 
Nuclear Regulatory Commission (NRC)
 
to the licensee. The TOCs will no longer
 
be included in the TSs and, as such, will no longer be part of Appendix A to
 
the Operating License.
Basis for proposed no significant hazards consideration determination:
 
As required by 10 CFR 50.91(a), the
 
licensee has provided its analysis of the
 
issue of no significant hazards
 
consideration, which is presented
 
below: 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously
 
evaluated?
Response: No.
 
The proposed amendment is administrative and affects control of a
 
document, the TOCs, listing the
 
specifications in the plant TSs. Transferring
 
control from the NRC to NextEra does not  
 
affect the operation, physical configuration, or function of plant equipment or systems.  
 
The proposed amendment does not impact
 
the initiators or assumptions of analyzed events, nor does it impact the mitigation of
 
accidents or transient events.
Therefore, the proposed amendment 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?
Response: No.  
 
The proposed amendment is administrative and does not alter plant
 
configuration, require installation of new  
 
equipment, alter assumptions about
 
previously analyzed accidents, or impact
 
operation or function of plant equipment or
 
systems. Therefore, this proposed amendment 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?
Response: No.  
 
The proposed amendment is administrative. The TOCs is not required by  
 
regulation to be in the TSs. Removal does not  
 
impact any safety assumptions or have the  
 
potential to reduce a margin of safety. The  
 
proposed amendment involves a transfer of  
 
control of the TOCs from the NRC to NextEra.  
 
No change in the technical content of the TSs  
 
is involved. Consequently, transfer from the  
 
NRC to NextEra has no impact on the margin  
 
of safety.
Therefore, the proposed amendment does not involve a significant reduction in a
 
margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on this review, it appears that the three
 
standards of 10 CFR 50.92(c) are
 
satisfied. Therefore, the NRC staff
 
proposes to determine that the VerDate Mar<15>2010 16:12 Jul 25, 2011Jkt 223001PO 00000Frm 00048Fmt 4703Sfmt 4703E:\FR\FM\26JYN1.SGM26JYN1 sroberts on DSK5SPTVN1PROD with NOTICES 44618 Federal Register/Vol. 76, No. 143/Tuesday, July 26, 2011/Notices amendment request involves no significant hazards consideration.
Attorney for licensee:
William Blair, Senior Attorney, NextEra Energy Point
 
Beach, LLC, P.O. Box 14000, Juno
 
Beach, FL 33408-0420.
NRC Branch Chief:
Robert J.
Pascarelli.
Virginia Electric and Power Company, Docket Nos. 50-338 and 50-339, North
 
Anna Power Station, Unit 1 and 2, Louisa County, Virginia Date of amendment request:
July 19, 2010, as supplemented September 9, 2010, January 26, May 16, and June 23, 2011. Description of amendment request:
Changes are proposed to the Technical
 
Specifications to include an analytical
 
methodology for the critical heat flux
 
correlation.
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 change involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No.
 
Approval of the proposed changes will allow Dominion to use the VIPRE [Versatile
 
Internals and Components Program for
 
Reactors-EPRI]-DIWRB-2M and VIPRE-
 
DIW-3 code/correlation pairs to perform
 
licensing calculations of Westinghouse RFA-
 
2 fuel in North Anna Cores, using the DDLs
 
[deterministic design limits] documented in
 
Appendix C of the DOM-NAF-2-A Fleet
 
Report and the SDL [statistical design limit]
 
documented herein. Neither the code/
 
correlation pair nor the Statistical Departure
 
from Nucleate Boiling Ratio (DNBR)
 
Evaluation Methodology affect accident
 
initiators and thus cannot increase the
 
probability of any accident. Further, since
 
both the deterministic and statistical DNBR
 
limits meet the required design basis of
 
avoiding Departure from Nucleate Boiling (DNB) with 95% probability at a 95%
 
confidence level, the use of the new code/
 
correlation and Statistical DNBR Evaluation
 
Methodology do not increase the potential
 
consequences of any accident. Finally, the
 
full core DNB design limit provides increased assurance that the consequences of a
 
postulated accident which includes
 
radioactive release would be minimized
 
because the overall number of rods in DNB
 
would not exceed the 0.1% level. The
 
pertinent evaluations to be performed as part
 
of the cycle specific reload safety analysis to
 
confirm that the existing safety analyses
 
remain applicable have been performed and
 
determined to be acceptable. The use of a
 
different code/correlation pair will not
 
increase the probability of an accident
 
because plant systems will not be operated in
 
a different manner, and system interfaces
 
will not change. The use of the VIPRE-DIWRB-2M and VIPRE-DIW-3 code/
correlation pairs to perform licensing
 
calculations of Westinghouse RFA-2 fuel in
 
North Anna cores will not result in a
 
measurable impact on normal operating plant
 
releases and will not increase the predicted
 
radiological consequences of accidents  
 
postulated in the UFSAR [Updated Final
 
Safety Analysis Report].
Therefore, neither the probability of occurrence nor the consequences of any accident previously evaluated is significantly
 
increased.
: 2. Does the change create the possibility of a new or different kind of accident from any
 
accident previously evaluated?
Response: No.
 
The proposed change does not involve a physical alteration of the plant (no new or
 
different type of equipment will be installed).
 
The use of VIPRE-D/WRB-2M and the
 
VIPRE-D/W-3 code/correlation pairs and the
 
applicable fuel design limits for DNBR does
 
not impact any of the applicable design
 
criteria and the licensing basis criteria will
 
continue to be met. Demonstrated adherence
 
to these standards and criteria precludes new
 
challenges to components and systems that
 
could introduce a new type of accident.
 
Setpoint safety analysis evaluations have
 
demonstrated that the use of VIPRE-D/WRB-
 
2M and VIPRE-D/W3 is acceptable. Design
 
and performance criteria will continue to be
 
met and no new single failure mechanisms
 
will be created. The use of the VIPRE-D/
 
WRB-2M and VIPRE-D/W-3 code/
 
correlation pairs and the Statistical DNBR
 
Evaluation Methodology does not involve
 
any alteration to plant equipment or
 
procedures that would introduce any new or
 
unique operational modes or accident
 
precursors. Thus, this change does not create
 
the possibility of a new or different kind of
 
accident from any accident previously
 
evaluated.
: 3. Does this change involve a significant reduction in a margin of safety?
Response: No.
 
Approval of the proposed changes will allow Dominion to use the VIPRE-D/WRB-
 
2M and VIPRE-D/W-3 code/correlation pairs
 
to perform licensing calculations of
 
Westinghouse RFA-2 fuel in North Anna
 
cores, using the DDLs documented in
 
Appendix C of the DOM-NAF-2-A Fleet
 
Report and the SDL documented herein. The  
 
SDL has been developed in accordance with
 
the Statistical DNBR Evaluation
 
Methodology. North Anna TS 2.1, ''Safety
 
Limits,'' specifies that any DNBR limit
 
established by any code/correlation must
 
provide at least 95% non-DNB probability at
 
a 95% confidence level. The DNBR limits
 
meet the design basis of avoiding DNB with
 
95% probability at a 95% confidence level.
 
The required DNBR margin of safety for
 
North Anna Power Station, which in this  
 
case is the margin between the 95/95 DNBR
 
limit and clad failure, is therefore not
 
reduced. Therefore, the proposed TS 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 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:
Gloria Kulesa.
Previously Published Notices of
 
Consideration of Issuance of
 
Amendments to Facility Operating
 
Licenses, Proposed No Significant
 
Hazards Consideration Determination, and Opportunity for a Hearing The following notices were previously published as separate individual
 
notices. The notice content was the
 
same as above. They were published as
 
individual notices either because time
 
did not allow the Commission to wait
 
for this biweekly notice or because the
 
action involved exigent circumstances.
 
They are repeated here because the
 
biweekly notice lists all amendments
 
issued or proposed to be issued
 
involving no significant hazards
 
consideration.
For details, see the individual notice in the Federal Register on the day and
 
page cited. This notice does not extend
 
the notice period of the original notice.
Arizona Public Service Company, et al., Docket Nos. STN 50-528, STN 50-529, and STN 50-530, Palo Verde Nuclear
 
Generating Station, Units 1, 2, and 3, Maricopa County, Arizona Date of amendment request:
August 27, 2010, as supplemented by letters
 
dated February 11 and May 25, 2011.
Brief description of amendment request: The proposed amendment would revise the feedwater line break
 
with loss of offsite power and single
 
failure (FWLB/LOP/SF) analysis
 
summarized in the Palo Verde Nuclear
 
Generating Station Updated Safety
 
Analysis Report. The revision would
 
change the credited operator action to
 
20 minutes from 30 minutes to control
 
the pressurizer level. The revision
 
would also revise the rate of reactor
 
coolant pump (RCP) bleed-off to the
 
reactor drain tank from three gallons per
 
minute to zero.
Date of publication of individual notice in Federal Register:
June 28, 2011 (76 FR 37853).
Expiration date of individual notice:
July 28, 2011, for comments and August
 
29, 2011, for hearings.
Notice of Issuance of Amendments to Facility Operating Licenses During the period since publication of the last biweekly notice, the VerDate Mar<15>2010 16:12 Jul 25, 2011Jkt 223001PO 00000Frm 00049Fmt 4703Sfmt 4703E:\FR\FM\26JYN1.SGM26JYN1 sroberts on DSK5SPTVN1PROD with NOTICES 44619 Federal Register/Vol. 76, No. 143/Tuesday, July 26, 2011/Notices Commission has issued the following amendments. The Commission has
 
determined for each of these
 
amendments that the application
 
complies with the standards and
 
requirements of the Atomic Energy Act
 
of 1954, as amended (the Act), and the
 
Commission's rules and regulations.
 
The Commission has made appropriate
 
findings as required by the Act and the
 
Commission's rules and regulations in
 
10 CFR Chapter I, which are set forth in
 
the license amendment.
Notice of Consideration of Issuance of Amendment to Facility Operating
 
License, Proposed No Significant
 
Hazards Consideration Determination, and Opportunity for A Hearing in
 
connection with these actions was
 
published in the Federal Register as indicated.
Unless otherwise indicated, the Commission has determined that these
 
amendments satisfy the criteria for
 
categorical exclusion in accordance
 
with 10 CFR 51.22. Therefore, pursuant
 
to 10 CFR 51.22(b), no environmental
 
impact statement or environmental
 
assessment need be prepared for these
 
amendments. If the Commission has
 
prepared an environmental assessment
 
under the special circumstances
 
provision in 10 CFR 51.22(b) and has
 
made a determination based on that
 
assessment, it is so indicated.
For further details with respect to the action see (1) The applications for
 
amendment, (2) the amendment, and (3)
 
the Commission's related letter, Safety
 
Evaluation and/or Environmental
 
Assessment as indicated. All of these
 
items are available for public inspection
 
at the NRC's Public Document Room (PDR), located at One White Flint North, Room O1-F21, 11555 Rockville Pike (first floor), Rockville, Maryland 20852.
 
Publicly available documents created or
 
received at the NRC are accessible
 
electronically through 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 pdr.resource@nrc.gov.
Exelon Generation Company, LLC, Docket Nos. STN 50-456 and STN 50-
 
457, Braidwood Station, Units 1 and 2, Will County, Illinois; Docket Nos. STN
 
50-454 and STN 50-455, Byron Station, Unit 1 and 2, Ogle County, Illinois Date of application for amendment:
June 29, 2010, as supplemented on
 
August 24, 2010, and January 13, 2011.
Brief description of amendment:
The license amendments revise Technical
 
Specifications (TS) Section 3.4.12, ''Low
 
Temperature Overpressure Protection (LTOP) System,'' to correct an
 
inconsistency between the TS, and
 
implementation of procedures and
 
administrative controls for Safety
 
Injection pumps required to mitigate a
 
postulated loss of decay heat removal
 
during mid-loop operation as discussed
 
in NRC Generic Letter 88-17, ''Loss of
 
Decay Heat Removal.''
Date of issuance:
June 29, 2011.
Effective date:
As of the date of issuance and shall be implemented within 60 days.
Amendment Nos.:
167, 167, 174, 174.
Facility Operating License Nos. NPF-72, NPF-77, NPF-37, and NPF-66:
The amendments revise the TSs and license.
Date of initial notice in Federal Register:
October 5, 2010 (75 FR 61526).
The August 24, 2010, and January 13, 2011, supplements 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 June 29, 2011.
No significant hazards consideration comments received:
No. Dated at Rockville, Maryland, this 15th day of July 2011.
For the Nuclear Regulatory Commission.
Joseph G. Giitter, Director, Division of Operating Reactor Licensing, Office of Nuclear Reactor
 
Regulation.
[FR Doc. 2011-18525 Filed 7-25-11; 8:45 am]
BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION
[ Docket No. 030-33305; License No. 25-10994-04; EA-10-258; NRC-2011-0163]
In the Matter of Bozeman Deaconess Foundation, dba Bozeman Deaconess
 
Hospital, Bozeman, MT; Confirmatory
 
Order Modifying License; (Effective
 
Immediately)
I Bozeman Deaconess Hospital (Licensee) is the holder of Materials License No. 25-10994-04 issued by the
 
Nuclear Regulatory Commission (NRC
 
or the Commission) pursuant to Title 10
 
of the Code of Federal Regulations (10
 
CFR) parts 30 and 35. The license
 
authorizes the operation of the
 
Licensee's facility in accordance with
 
the conditions specified therein, at 915
 
Highland Boulevard, Bozeman, Montana. This Confirmatory Order is the result of an agreement reached during an alternative dispute resolution (ADR)
 
mediation session conducted on May
 
25, 2011, at the NRC Region IV offices
 
in Arlington, Texas.
II On January 27, 2010, the NRC conducted a routine unannounced inspection of the Bozeman Deaconess
 
Hospital facility to evaluate radiation
 
safety and security, as well as
 
compliance with Commission rules and
 
regulations and the conditions of the
 
license. During the inspection, it was
 
determined that an employee of
 
Bozeman Deaconess Hospital failed to
 
secure radioactive materials from
 
unauthorized access or removal from
 
the facility's nuclear medicine
 
laboratory (hot lab). On March 8, 2010, the NRC Office of Investigations (OI),
Region IV, began an investigation (OI
 
Case No. 4-2010-033) to determine
 
whether employees from Bozeman
 
Deaconess Hospital willfully failed to
 
secure radioactive material during
 
periods when authorized personnel
 
were absent from the hot lab. Based on
 
the results of the inspection and the
 
evidence developed during the
 
investigation, the NRC identified two
 
apparent violations. The first apparent
 
violation involved a willful failure to
 
secure licensed materials from
 
unauthorized removal or access as
 
required by 10 CFR 20.1801. The second
 
violation involved a failure to control
 
and maintain constant surveillance of
 
licensed material as required by 10 CFR
 
20.1802. By letter dated April 12, 2011, the NRC transmitted the results of the
 
inspection and a factual summary of
 
OI's Investigation Report 4-2010-033 to
 
Bozeman Deaconess Hospital. In the
 
April 12 letter, the NRC informed the
 
Licensee that the NRC was considering escalated enforcement action for the
 
apparent violations. The NRC offered
 
the Licensee the opportunity to request
 
a predecisional enforcement conference
 
or request ADR with the NRC in an
 
attempt to resolve issues associated with
 
this matter. In response, on April 21, 2011, Bozeman Deaconess Hospital
 
requested ADR to resolve this matter
 
with the NRC.
On May 25, 2011, the NRC and Licensee representatives met in an ADR
 
session with a professional mediator, arranged through the Cornell University
 
Institute on Conflict Resolution. ADR is
 
a process in which a neutral mediator
 
with no decision-making authority
 
assists the parties in reaching an


agreement on resolving any differences
44618                          Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices amendment request involves no                            DIWRB-2M and VIPRE-DIW-3 code/                        standards of 50.92(c) are satisfied.
significant hazards consideration.                      correlation pairs to perform licensing                Therefore, the NRC staff proposes to Attorney for licensee: William Blair,                  calculations of Westinghouse RFA-2 fuel in            determine that the amendment request Senior Attorney, NextEra Energy Point                    North Anna cores will not result in a measurable impact on normal operating plant involves no significant hazards Beach, LLC, P.O. Box 14000, Juno                        releases and will not increase the predicted          consideration.
Beach, FL 33408-0420.                                    radiological consequences of accidents                  Attorney for licensee: Lillian M.
NRC Branch Chief: Robert J.                            postulated in the UFSAR [Updated Final                Cuoco, Senior Counsel, Dominion Pascarelli.                                              Safety Analysis Report].                              Resources Services, Inc., 120 Tredegar Therefore, neither the probability of              Street, RS-2, Richmond, VA 23219.
Virginia Electric and Power Company,                    occurrence nor the consequences of any                 NRC Branch Chief: Gloria Kulesa.
Docket Nos. 50-338 and 50-339, North                    accident previously evaluated is significantly Anna Power Station, Unit 1 and 2,                        increased.                                            Previously Published Notices of Louisa County, Virginia                                    2. Does the change create the possibility of      Consideration of Issuance of a new or different kind of accident from any          Amendments to Facility Operating Date of amendment request: July 19, accident previously evaluated?                        Licenses, Proposed No Significant 2010, as supplemented September 9,                          Response: No.
2010, January 26, May 16, and June 23,                                                                        Hazards Consideration Determination, The proposed change does not involve a 2011.                                                    physical alteration of the plant (no new or and Opportunity for a Hearing Description of amendment request:                    different type of equipment will be installed).          The following notices were previously Changes are proposed to the Technical                    The use of VIPRE-D/WRB-2M and the                    published as separate individual Specifications to include an analytical                  VIPRE-D/W-3 code/correlation pairs and the            notices. The notice content was the methodology for the critical heat flux                  applicable fuel design limits for DNBR does          same as above. They were published as correlation.                                            not impact any of the applicable design criteria and the licensing basis criteria will individual notices either because time Basis for proposed no significant                                                                          did not allow the Commission to wait continue to be met. Demonstrated adherence hazards consideration determination:                    to these standards and criteria precludes new        for this biweekly notice or because the As required by 10 CFR 50.91(a), the                      challenges to components and systems that            action involved exigent circumstances.
licensee has provided its analysis of the                could introduce a new type of accident.              They are repeated here because the issue of no significant hazards                          Setpoint safety analysis evaluations have            biweekly notice lists all amendments consideration, which is presented                        demonstrated that the use of VIPRE-D/WRB-            issued or proposed to be issued below:                                                  2M and VIPRE-D/W3 is acceptable. Design              involving no significant hazards and performance criteria will continue to be
: 1. Does the change involve a significant              met and no new single failure mechanisms consideration.
increase in the probability or consequences              will be created. The use of the VIPRE-D/                For details, see the individual notice of an accident previously evaluated?                    WRB-2M and VIPRE-D/W-3 code/                          in the Federal Register on the day and Response: No.                                        correlation pairs and the Statistical DNBR            page cited. This notice does not extend Approval of the proposed changes will                Evaluation Methodology does not involve              the notice period of the original notice.
allow Dominion to use the VIPRE [Versatile              any alteration to plant equipment or Internals and Components Program for                    procedures that would introduce any new or            Arizona Public Service Company, et al.,
ReactorsEPRI]-DIWRB-2M and VIPRE-                      unique operational modes or accident                  Docket Nos. STN 50-528, STN 50-529, DIW-3 code/correlation pairs to perform                  precursors. Thus, this change does not create        and STN 50-530, Palo Verde Nuclear licensing calculations of Westinghouse RFA-              the possibility of a new or different kind of        Generating Station, Units 1, 2, and 3, 2 fuel in North Anna Cores, using the DDLs              accident from any accident previously
[deterministic design limits] documented in Maricopa County, Arizona evaluated.
Appendix C of the DOM-NAF-2-A Fleet                        3. Does this change involve a significant            Date of amendment request: August Report and the SDL [statistical design limit]            reduction in a margin of safety?                      27, 2010, as supplemented by letters documented herein. Neither the code/                        Response: No.                                      dated February 11 and May 25, 2011.
correlation pair nor the Statistical Departure              Approval of the proposed changes will                Brief description of amendment from Nucleate Boiling Ratio (DNBR)                      allow Dominion to use the VIPRE-D/WRB-                request: The proposed amendment Evaluation Methodology affect accident                  2M and VIPRE-D/W-3 code/correlation pairs initiators and thus cannot increase the                                                                        would revise the feedwater line break to perform licensing calculations of                  with loss of offsite power and single probability of any accident. Further, since              Westinghouse RFA-2 fuel in North Anna both the deterministic and statistical DNBR                                                                    failure (FWLB/LOP/SF) analysis cores, using the DDLs documented in limits meet the required design basis of                Appendix C of the DOM-NAF-2-A Fleet                  summarized in the Palo Verde Nuclear avoiding Departure from Nucleate Boiling                Report and the SDL documented herein. The            Generating Station Updated Safety (DNB) with 95% probability at a 95%                      SDL has been developed in accordance with            Analysis Report. The revision would confidence level, the use of the new code/              the Statistical DNBR Evaluation                      change the credited operator action to correlation and Statistical DNBR Evaluation              Methodology. North Anna TS 2.1, Safety              20 minutes from 30 minutes to control Methodology do not increase the potential                Limits, specifies that any DNBR limit consequences of any accident. Finally, the                                                                    the pressurizer level. The revision established by any code/correlation must              would also revise the rate of reactor full core DNB design limit provides increased            provide at least 95% non-DNB probability at assurance that the consequences of a                                                                          coolant pump (RCP) bleed-off to the a 95% confidence level. The DNBR limits postulated accident which includes                      meet the design basis of avoiding DNB with            reactor drain tank from three gallons per radioactive release would be minimized                  95% probability at a 95% confidence level.            minute to zero.
because the overall number of rods in DNB                The required DNBR margin of safety for                  Date of publication of individual would not exceed the 0.1% level. The                    North Anna Power Station, which in this              notice in Federal Register: June 28, pertinent evaluations to be performed as part            case is the margin between the 95/95 DNBR            2011 (76 FR 37853).
of the cycle specific reload safety analysis to          limit and clad failure, is therefore not                Expiration date of individual notice:
sroberts on DSK5SPTVN1PROD with NOTICES confirm that the existing safety analyses                reduced.
remain applicable have been performed and July 28, 2011, for comments and August Therefore, the proposed TS change does            29, 2011, for hearings.
determined to be acceptable. The use of a                not involve a significant reduction in a different code/correlation pair will not                margin of safety.                                    Notice of Issuance of Amendments to increase the probability of an accident                                                                        Facility Operating Licenses because plant systems will not be operated in              The NRC staff has reviewed the a different manner, and system interfaces                licensees analysis and, based on this                  During the period since publication of will not change. The use of the VIPRE-                  review, it appears that the three                    the last biweekly notice, the VerDate Mar<15>2010  16:12 Jul 25, 2011  Jkt 223001  PO 00000  Frm 00049  Fmt 4703  Sfmt 4703  E:\FR\FM\26JYN1.SGM  26JYN1


regarding the dispute. This VerDate Mar<15>2010 16:12 Jul 25, 2011Jkt 223001PO 00000Frm 00050Fmt 4703Sfmt 4703E:\FR\FM\26JYN1.SGM26JYN1 sroberts on DSK5SPTVN1PROD with NOTICES}}
Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices                                          44619 Commission has issued the following                        Brief description of amendment: The                  This Confirmatory Order is the result amendments. The Commission has                          license amendments revise Technical                  of an agreement reached during an determined for each of these                            Specifications (TS) Section 3.4.12, Low            alternative dispute resolution (ADR) amendments that the application                          Temperature Overpressure Protection                  mediation session conducted on May complies with the standards and                          (LTOP) System, to correct an                        25, 2011, at the NRC Region IV offices requirements of the Atomic Energy Act                    inconsistency between the TS, and                    in Arlington, Texas.
of 1954, as amended (the Act), and the                  implementation of procedures and                      II Commissions rules and regulations.                      administrative controls for Safety The Commission has made appropriate                      Injection pumps required to mitigate a                  On January 27, 2010, the NRC findings as required by the Act and the                  postulated loss of decay heat removal                conducted a routine unannounced Commissions rules and regulations in                    during mid-loop operation as discussed                inspection of the Bozeman Deaconess 10 CFR Chapter I, which are set forth in                in NRC Generic Letter 88-17, Loss of                Hospital facility to evaluate radiation the license amendment.                                  Decay Heat Removal.                                safety and security, as well as Notice of Consideration of Issuance of                  Date of issuance: June 29, 2011.                  compliance with Commission rules and Amendment to Facility Operating                            Effective date: As of the date of                  regulations and the conditions of the License, Proposed No Significant                        issuance and shall be implemented                    license. During the inspection, it was Hazards Consideration Determination,                    within 60 days.                                      determined that an employee of and Opportunity for A Hearing in                            Amendment Nos.: 167, 167, 174, 174.                Bozeman Deaconess Hospital failed to connection with these actions was                          Facility Operating License Nos. NPF-              secure radioactive materials from published in the Federal Register as                    72, NPF-77, NPF-37, and NPF-66: The                  unauthorized access or removal from amendments revise the TSs and license.                the facilitys nuclear medicine indicated.
Date of initial notice in Federal                  laboratory (hot lab). On March 8, 2010, Unless otherwise indicated, the                                                                            the NRC Office of Investigations (OI),
Commission has determined that these                    Register: October 5, 2010 (75 FR 61526).
The August 24, 2010, and January 13,                  Region IV, began an investigation (OI amendments satisfy the criteria for                                                                            Case No. 4-2010-033) to determine categorical exclusion in accordance                      2011, supplements contained clarifying information and did not change the NRC                whether employees from Bozeman with 10 CFR 51.22. Therefore, pursuant                                                                        Deaconess Hospital willfully failed to to 10 CFR 51.22(b), no environmental                    staffs initial proposed finding of no significant hazards consideration.                    secure radioactive material during impact statement or environmental                                                                              periods when authorized personnel assessment need be prepared for these                      The Commissions related evaluation of the amendments is contained in a                  were absent from the hot lab. Based on amendments. If the Commission has                                                                              the results of the inspection and the prepared an environmental assessment                    safety evaluation dated June 29, 2011.
No significant hazards consideration              evidence developed during the under the special circumstances                                                                                investigation, the NRC identified two provision in 10 CFR 51.22(b) and has                    comments received: No.
apparent violations. The first apparent made a determination based on that                        Dated at Rockville, Maryland, this 15th day violation involved a willful failure to assessment, it is so indicated.                          of July 2011.
secure licensed materials from For further details with respect to the                For the Nuclear Regulatory Commission.
unauthorized removal or access as action see (1) The applications for                      Joseph G. Giitter,                                    required by 10 CFR 20.1801. The second amendment, (2) the amendment, and (3)                    Director, Division of Operating Reactor              violation involved a failure to control the Commissions related letter, Safety                  Licensing, Office of Nuclear Reactor                  and maintain constant surveillance of Evaluation and/or Environmental                          Regulation.                                          licensed material as required by 10 CFR Assessment as indicated. All of these                    [FR Doc. 2011-18525 Filed 7-25-11; 8:45 am]          20.1802.
items are available for public inspection                BILLING CODE 7590-01-P                                  By letter dated April 12, 2011, the at the NRCs Public Document Room                                                                              NRC transmitted the results of the (PDR), located at One White Flint North,                                                                      inspection and a factual summary of Room O1-F21, 11555 Rockville Pike                        NUCLEAR REGULATORY                                    OIs Investigation Report 4-2010-033 to (first floor), Rockville, Maryland 20852.                COMMISSION                                            Bozeman Deaconess Hospital. In the Publicly available documents created or                  [ Docket No. 030-33305; License No. 25-              April 12 letter, the NRC informed the received at the NRC are accessible                      10994-04; EA-10-258; NRC-2011-0163]                  Licensee that the NRC was considering electronically through the Agencywide                                                                          escalated enforcement action for the Documents Access and Management                          In the Matter of Bozeman Deaconess                    apparent violations. The NRC offered System (ADAMS) in the NRC Library at                    Foundation, dba Bozeman Deaconess                    the Licensee the opportunity to request http://www.nrc.gov/reading-rm/                          Hospital, Bozeman, MT; Confirmatory                  a predecisional enforcement conference adams.html. If you do not have access                    Order Modifying License; (Effective                  or request ADR with the NRC in an to ADAMS or if there are problems in                    Immediately)                                          attempt to resolve issues associated with accessing the documents located in                                                                            this matter. In response, on April 21, ADAMS, contact the PDR Reference                        I                                                    2011, Bozeman Deaconess Hospital staff at 1-800-397-4209, 301-415-4737                      Bozeman Deaconess Hospital                          requested ADR to resolve this matter or by email to pdr.resource@nrc.gov.                    (Licensee) is the holder of Materials                with the NRC.
License No. 25-10994-04 issued by the                    On May 25, 2011, the NRC and Exelon Generation Company, LLC, Nuclear Regulatory Commission (NRC                    Licensee representatives met in an ADR Docket Nos. STN 50-456 and STN 50-or the Commission) pursuant to Title 10              session with a professional mediator, sroberts on DSK5SPTVN1PROD with NOTICES 457, Braidwood Station, Units 1 and 2, of the Code of Federal Regulations (10                arranged through the Cornell University Will County, Illinois; Docket Nos. STN CFR) parts 30 and 35. The license                    Institute on Conflict Resolution. ADR is 50-454 and STN 50-455, Byron Station, authorizes the operation of the                      a process in which a neutral mediator Unit 1 and 2, Ogle County, Illinois Licensees facility in accordance with                with no decision-making authority Date of application for amendment:                    the conditions specified therein, at 915              assists the parties in reaching an June 29, 2010, as supplemented on                        Highland Boulevard, Bozeman,                          agreement on resolving any differences August 24, 2010, and January 13, 2011.                  Montana.                                              regarding the dispute. This VerDate Mar<15>2010   16:12 Jul 25, 2011  Jkt 223001  PO 00000  Frm 00050  Fmt 4703  Sfmt 4703  E:\FR\FM\26JYN1.SGM  26JYN1}}

Revision as of 17:24, 12 November 2019

July 26, 2011 Applications and Amendments to Facility Operating Licenses Involving No Significant Hazards Considerations
ML11196A022
Person / Time
Site: Palo Verde, Point Beach, Byron, Braidwood, North Anna, River Bend  NextEra Energy icon.png
Issue date: 07/15/2011
From: Giitter J
Division of Operating Reactor Licensing
To:
Clayton B
References
76FR44614, NRC20110167
Download: ML11196A022 (21)


Text

44614 Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices fixtures, and electronic equipment. For costing $10,000 or less used in and their comments that they do not want many of these incidental items, U.S. incorporated into the project. With this publicly disclosed.

manufactured alternatives are not exemption, the agency hereby You may submit comments by any always readily or reasonably available. establishes a $1.5M ceiling for the total one of the following methods.

The miscellaneous character of these allowable value of de minimis

  • Federal Rulemaking Web site: Go to manufactured goods, together with their exemptions used on this project. http://www.regulations.gov and search low individual cost, characterize them for documents filed under Docket ID Dated: July 7, 2011.

as items incidental to the project. NRC-NRC-2011-0167. Address Lawrence Rudolph, Requiring individual exemptions for questions about NRC dockets to Carol General Counsel. Gallagher 301-492-3668; e-mail low cost, incidental items would be time prohibitive and overly burdensome [FR Doc. 2011-18643 Filed 7-25-11; 8:45 am] Carol.Gallagher@nrc.gov.

for the awardee (University of Alaska, BILLING CODE 7555-01-P

  • Mail comments to: Chief, Rules, Fairbanks), subcontractor (shipyard) and Announcements, and Directives Branch for NSF. Such a de minimis exemption (RADB), Office of Administration, Mail allows the award recipients to focus NUCLEAR REGULATORY Stop: TWB-05-B01M, U.S. Nuclear their efforts on the major manufactured COMMISSION Regulatory Commission, Washington, goods within the ARRV project. The DC 20555-0001.

[NRC-2011-0167]

terms and conditions of the award still

  • Fax comments to: RADB at 301-require UAF to Buy American to the Biweekly Notice; Applications and 492-3446.

extent practicable for items less than Amendments to Facility Operating You can access publicly available

$10,000. Therefore, a limited project- Licenses Involving No Significant documents related to this notice using specific de minimis exemption for any Hazards Considerations the following methods:

such incidental item costing $10,000 or

  • NRCs Public Document Room less used in and incorporated into the Background (PDR): The public may examine and ARRV project is justified in the public have copied, for a fee, publicly available Pursuant to Section 189a. (2) of the interest. The Department of Energy has documents at the NRCs PDR, Room O1-Atomic Energy Act of 1954, as amended issued a similar type of de minimis F21, One White Flint North, 11555 (the Act), the U.S. Nuclear Regulatory exemption, relating to its Office of Rockville Pike, Rockville, Maryland Commission (the Commission or NRC)

Energy Efficiency and Renewable 20852.

is publishing this regular biweekly

  • NRCs Agencywide Documents Energy [75 FR 35447 (June 22, 2010)]. notice. The Act requires the At this phase in the ARRV project, it Access and Management System Commission publish notice of any (ADAMS): Publicly available documents is estimated that only $750,000 of amendments issued, or proposed to be incidental items will require use of the created or received at the NRC are issued and grants the Commission the accessible electronically through de minimis exemption. To ensure authority to issue and make proper oversight with regard to use of ADAMS in the NRC Library at http://

immediately effective any amendment www.nrc.gov/reading-rm/adams.html.

this exemption within the project, the to an operating license upon a agency hereby establishes an allowable From this page, the public can gain determination by the Commission that entry into ADAMS, which provides text ceiling of $1.5M for the application of such amendment involves no significant and image files of the NRCs public this de minimis exemption; this hazards consideration, notwithstanding documents. If you do not have access to represents approximately 2.5% of the the pendency before the Commission of ADAMS or if there are problems in total value of materials used in the a request for a hearing from any person. accessing the documents located in vessel. (Since the previously-granted This biweekly notice includes all ADAMS, contact the NRCs PDR exemptions for the purchase of ARRV notices of amendments issued, or reference staff at 1-800-397-4209, 301-equipment were not granted on this de proposed to be issued from June 30, 415-4737, or by e-mail to minimis basis, but instead because there 2011 to July 13, 2011. The last biweekly pdr.resource@nrc.gov.

was not a domestic manufacturer of the notice was published on July 12, 2011

  • Federal Rulemaking Web site:

qualifying equipment, those purchases (76 FR 40937). Public comments and supporting do not fall within the $1.5M ceiling for the use of this de minimis exemption.) ADDRESSES: Please include Docket ID materials related to this notice can be Issuance of this limited project- NRC-2011-0167 in the subject line of found at http://www.regulations.gov by specific exemption recognizes NSFs your comments. Comments submitted in searching on Docket ID: NRC-2011-commitment to expeditious spending of writing or in electronic form will be 0167.

Recovery Act dollars balanced against posted on the NRC Web site and on the Federal rulemaking Web site http:// Notice of Consideration of Issuance of the need for efficient implementation of www.regulations.gov. Because your Amendments to Facility Operating the Recovery Act provision while still comments will not be edited to remove Licenses, Proposed No Significant maintaining the Buy American any identifying or contact information, Hazards Consideration Determination, requirements for manufactured goods the NRC cautions you against including and Opportunity for a Hearing that are greater than the de minimis amount of $10,000. any information in your submission that The Commission has made a you do not want to be publicly proposed determination that the III. Exemption disclosed. following amendment requests involve On July 6, 2011, and under the The NRC requests that any party no significant hazards consideration.

sroberts on DSK5SPTVN1PROD with NOTICES authority of section 1605(b)(1) of the soliciting or aggregating comments Under the Commissions regulations in Public Law 111-5 and delegation order received from other persons for Title 10 of the Code of Federal dated 27 May 2010, with respect to the submission to the NRC inform those Regulations (10 CFR), 50.92, this means Alaska Region Research Vessel Project persons that the NRC will not edit their that operation of the facility in funded by NSF, the NSF Chief Financial comments to remove any identifying or accordance with the proposed Officer granted a limited project contact information, and therefore, they amendment would not (1) Involve a exemption for any incidental item should not include any information in significant increase in the probability or VerDate Mar<15>2010 16:12 Jul 25, 2011 Jkt 223001 PO 00000 Frm 00045 Fmt 4703 Sfmt 4703 E:\FR\FM\26JYN1.SGM 26JYN1

Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices 44615 consequences of an accident previously Chief Administrative Judge of the If a hearing is requested, the evaluated; or (2) create the possibility of Atomic Safety and Licensing Board Commission will make a final a new or different kind of accident from Panel, will rule on the request and/or determination on the issue of no any accident previously evaluated; or petition; and the Secretary or the Chief significant hazards consideration. The (3) involve a significant reduction in a Administrative Judge of the Atomic final determination will serve to decide margin of safety. The basis for this Safety and Licensing Board will issue a when the hearing is held. If the final proposed determination for each notice of a hearing or an appropriate determination is that the amendment amendment request is shown below. order. request involves no significant hazards The Commission is seeking public As required by 10 CFR 2.309, a consideration, the Commission may comments on this proposed petition for leave to intervene shall set issue the amendment and make it determination. Any comments received forth with particularity the interest of immediately effective, notwithstanding within 30 days after the date of the petitioner in the proceeding, and the request for a hearing. Any hearing publication of this notice will be how that interest may be affected by the held would take place after issuance of considered in making any final results of the proceeding. The petition the amendment. If the final determination. should specifically explain the reasons determination is that the amendment Normally, the Commission will not why intervention should be permitted request involves a significant hazards issue the amendment until the with particular reference to the consideration, then any hearing held expiration of 60 days after the date of following general requirements: (1) The would take place before the issuance of publication of this notice. The name, address, and telephone number of any amendment.

Commission may issue the license the requestor or petitioner; (2) the All documents filed in NRC amendment before expiration of the 60- nature of the requestors/petitioners adjudicatory proceedings, including a day period provided that its final right under the Act to be made a party request for hearing, a petition for leave determination is that the amendment to the proceeding; (3) the nature and to intervene, any motion or other involves no significant hazards extent of the requestors/petitioners document filed in the proceeding prior consideration. In addition, the property, financial, or other interest in to the submission of a request for Commission may issue the amendment the proceeding; and (4) the possible hearing or petition to intervene, and prior to the expiration of the 30-day effect of any decision or order which documents filed by interested comment period should circumstances may be entered in the proceeding on the governmental entities participating change during the 30-day comment requestors/petitioners interest. The under 10 CFR 2.315(c), must be filed in period such that failure to act in a petition must also identify the specific accordance with the NRC E-Filing rule timely way would result, for example in contentions which the requestor/ (72 FR 49139, August 28, 2007). The E-derating or shutdown of the facility. petitioner seeks to have litigated at the Filing process requires participants to Should the Commission take action proceeding. submit and serve all adjudicatory prior to the expiration of either the Each contention must consist of a documents over the internet, or in some comment period or the notice period, it specific statement of the issue of law or cases to mail copies on electronic will publish in the Federal Register a fact to be raised or controverted. In storage media. Participants may not notice of issuance. Should the addition, the requestor/petitioner shall submit paper copies of their filings Commission make a final No Significant provide a brief explanation of the bases unless they seek an exemption in Hazards Consideration Determination, for the contention and a concise accordance with the procedures any hearing will take place after statement of the alleged facts or expert described below.

issuance. The Commission expects that opinion which support the contention To comply with the procedural the need to take this action will occur and on which the requestor/petitioner requirements of E-Filing, at least 10 very infrequently. intends to rely in proving the contention days prior to the filing deadline, the Within 60 days after the date of at the hearing. The requestor/petitioner participant should contact the Office of publication of this notice, any person(s) must also provide references to those the Secretary by e-mail at whose interest may be affected by this specific sources and documents of hearing.docket@nrc.gov, or by telephone action may file a request for a hearing which the petitioner is aware and on at 301-415-1677, to request (1) a digital and a petition to intervene with respect which the requestor/petitioner intends identification (ID) certificate, which to issuance of the amendment to the to rely to establish those facts or expert allows the participant (or its counsel or subject facility operating license. opinion. The petition must include representative) to digitally sign Requests for a hearing and a petition for sufficient information to show that a documents and access the E-Submittal leave to intervene shall be filed in genuine dispute exists with the server for any proceeding in which it is accordance with the Commissions applicant on a material issue of law or participating; and (2) advise the Rules of Practice for Domestic fact. Contentions shall be limited to Secretary that the participant will be Licensing Proceedings in 10 CFR part matters within the scope of the submitting a request or petition for

2. Interested person(s) should consult a amendment under consideration. The hearing (even in instances in which the current copy of 10 CFR 2.309, which is contention must be one which, if participant, or its counsel or available at the NRCs PDR, located at proven, would entitle the requestor/ representative, already holds an NRC-One White Flint North, Room O1-F21, petitioner to relief. A requestor/ issued digital ID certificate). Based upon 11555 Rockville Pike (first floor), petitioner who fails to satisfy these this information, the Secretary will Rockville, Maryland 20852. NRC requirements with respect to at least one establish an electronic docket for the regulations are accessible electronically contention will not be permitted to hearing in this proceeding if the sroberts on DSK5SPTVN1PROD with NOTICES from the NRC Library on the NRC Web participate as a party. Secretary has not already established an site at http://www.nrc.gov/reading-rm/ Those permitted to intervene become electronic docket.

doc-collections/cfr/. If a request for a parties to the proceeding, subject to any Information about applying for a hearing or petition for leave to intervene limitations in the order granting leave to digital ID certificate is available on is filed by the above date, the intervene, and have the opportunity to NRCs public Web site at http://

Commission or a presiding officer participate fully in the conduct of the www.nrc.gov/site-help/e-submittals/

designated by the Commission or by the hearing. apply-certificates.html. System VerDate Mar<15>2010 16:12 Jul 25, 2011 Jkt 223001 PO 00000 Frm 00046 Fmt 4703 Sfmt 4703 E:\FR\FM\26JYN1.SGM 26JYN1

44616 Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices requirements for accessing the E- Desk through the Contact Us link timely filings will not be entertained Submittal server are detailed in NRCs located on the NRC Web site at http:// absent a determination by the presiding Guidance for Electronic Submission, www.nrc.gov/site-help/e- officer that the petition or request which is available on the agencys submittals.html, by e-mail at should be granted or the contentions public Web site at http://www.nrc.gov/ MSHD.Resource@nrc.gov, or by a toll- should be admitted, based on a site-help/e-submittals.html. Participants free call at 1-866-672-7640. The NRC balancing of the factors specified in 10 may attempt to use other software not Meta System Help Desk is available CFR 2.309(c)(1)(i)-(viii).

listed on the Web site, but should note between 8 a.m. and 8 p.m., Eastern For further details with respect to this that the NRCs E-Filing system does not Time, Monday through Friday, license amendment application, see the support unlisted software, and the NRC excluding government holidays. application for amendment which is Meta System Help Desk will not be able Participants who believe that they available for public inspection at the to offer assistance in using unlisted have a good cause for not submitting NRCs PDR, located at One White Flint software. documents electronically must file an North, Room O1-F21, 11555 Rockville If a participant is electronically exemption request, in accordance with Pike (first floor), Rockville, Maryland submitting a document to the NRC in 10 CFR 2.302(g), with their initial paper 20852. Publicly available documents accordance with the E-Filing rule, the filing requesting authorization to created or received at the NRC are participant must file the document continue to submit documents in paper accessible electronically through using the NRCs online, Web-based format. Such filings must be submitted ADAMS in the NRC Library at http://

submission form. In order to serve by: (1) first class mail addressed to the www.nrc.gov/reading-rm/adams.html.

documents through the Electronic Office of the Secretary of the Persons who do not have access to Information Exchange System, users Commission, U.S. Nuclear Regulatory ADAMS or who encounter problems in will be required to install a Web Commission, Washington, DC 20555- accessing the documents located in browser plug-in from the NRC Web site. 0001, Attention: Rulemaking and ADAMS, should contact the NRC PDR Further information on the Web-based Adjudications Staff; or (2) courier, Reference staff at 1-800-397-4209, 301-submission form, including the express mail, or expedited delivery 415-4737, or by e-mail to installation of the Web browser plug-in, service to the Office of the Secretary, pdr.resource@nrc.gov.

is available on the NRCs public Web Sixteenth Floor, One White Flint North, site at http://www.nrc.gov/site-help/e- 11555 Rockville Pike, Rockville, Entergy Gulf States Louisiana, LLC, and submittals.html. Maryland 20852, Attention: Rulemaking Entergy Operations, Inc., Docket No.

Once a participant has obtained a and Adjudications Staff. Participants 50-458, River Bend Station, Unit 1, digital ID certificate and a docket has filing a document in this manner are West Feliciana Parish, Louisiana been created, the participant can then responsible for serving the document on Date of amendment request: June 10, submit a request for hearing or petition all other participants. Filing is 2011.

for leave to intervene. Submissions considered complete by first-class mail should be in Portable Document Format Description of amendment request:

as of the time of deposit in the mail, or (PDF) in accordance with NRC guidance The proposed amendment would revise by courier, express mail, or expedited available on the NRC public Web site at delivery service upon depositing the the Technical Specifications (TSs) to http://www.nrc.gov/site-help/e- document with the provider of the add a new limiting condition for submittals.html. A filing is considered service. A presiding officer, having operation (LCO) Applicability complete at the time the documents are granted an exemption request from requirement, LCO 3.0.9, and its submitted through the NRCs E-Filing using E-Filing, may require a participant associated Bases, relating to the system. To be timely, an electronic or party to use E-Filing if the presiding modification of requirements regarding filing must be submitted to the E-Filing officer subsequently determines that the the impact of unavailable barriers, not system no later than 11:59 p.m. Eastern reason for granting the exemption from explicitly addressed in TSs, but Time on the due date. Upon receipt of use of E-Filing no longer exists. required for operability of supported a transmission, the E-Filing system Documents submitted in adjudicatory systems in TSs. This change is time-stamps the document and sends proceedings will appear in NRCs consistent with NRC-approved the submitter an e-mail notice electronic hearing docket which is Technical Specification Task Force confirming receipt of the document. The available to the public at http:// (TSTF) Improved Standard Technical E-Filing system also distributes an e- ehd1.nrc.gov/EHD/, unless excluded Specification Change Traveler, TSTF-mail notice that provides access to the pursuant to an order of the Commission, 427, Revision 2, Allowance for Non document to the NRC Office of the or the presiding officer. Participants are Technical Specification Barrier General Counsel and any others who requested not to include personal Degradation on Supported System have advised the Office of the Secretary privacy information, such as social OPERABILITY.

that they wish to participate in the security numbers, home addresses, or The NRC staff issued a Notice of proceeding, so that the filer need not home phone numbers in their filings, Opportunity to Comment in the Federal serve the documents on those unless an NRC regulation or other law Register on June 2, 2006 (71 FR 32145),

participants separately. Therefore, requires submission of such on possible amendments to revise the applicants and other participants (or information. With respect to plant-specific TSs, including a model their counsel or representative) must copyrighted works, except for limited safety evaluation and model no apply for and receive a digital ID excerpts that serve the purpose of the significant hazards consideration certificate before a hearing request/ adjudicatory filings and would determination using the consolidated sroberts on DSK5SPTVN1PROD with NOTICES petition to intervene is filed so that they constitute a Fair Use application, line item improvement process. The can obtain access to the document via participants are requested not to include NRC staff subsequently issued a Notice the E-Filing system. copyrighted materials in their of Availability of this TS improvement A person filing electronically using submission. in the Federal Register on October 3, the agencys adjudicatory E-Filing Petitions for leave to intervene must 2006 (71 FR 58444). The licensee system may seek assistance by be filed no later than 60 days from the affirmed the applicability of the model contacting the NRC Meta System Help date of publication of this notice. Non- no significant hazards consideration VerDate Mar<15>2010 16:12 Jul 25, 2011 Jkt 223001 PO 00000 Frm 00047 Fmt 4703 Sfmt 4703 E:\FR\FM\26JYN1.SGM 26JYN1

Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices 44617 determination in its application dated Criterion 3The Proposed Change Does maintenance and issuance of updates to June 10, 2011. Not Involve a Significant Reduction in the TOCs will transfer from the U.S.

Basis for proposed no significant the Margin of Safety Nuclear Regulatory Commission (NRC) hazards consideration determination: to the licensee. The TOCs will no longer The proposed change allows a delay As required by 10 CFR 50.91(a), an be included in the TSs and, as such, time for entering a supported system TS analysis of the issue of no significant will no longer be part of Appendix A to when the inoperability is due solely to hazards consideration is presented the Operating License.

an unavailable barrier, if risk is assessed below: Basis for proposed no significant and managed. The postulated initiating Criterion 1The Proposed Change Does hazards consideration determination:

events which may require a functional Not Involve a Significant Increase in the As required by 10 CFR 50.91(a), the barrier are limited to those with low Probability or Consequences of an licensee has provided its analysis of the frequencies of occurrence, and the Accident Previously Evaluated issue of no significant hazards overall TS system safety function would consideration, which is presented The proposed change allows a delay still be available for the majority of below:

time for entering a supported system anticipated challenges. The risk impact technical specification (TS) when the of the proposed TS changes was 1. Does the proposed amendment involve assessed following the three-tiered a significant increase in the probability or inoperability is due solely to an consequences of an accident previously unavailable barrier if risk is assessed approach recommended in [NRC evaluated?

and managed. The postulated initiating Regulatory Guide (RG) 1.177, An Response: No.

events which may require a functional Approach for Plant-Specific, Risk- The proposed amendment is barrier are limited to those with low Informed Decisionmaking: Technical administrative and affects control of a frequencies of occurrence, and the Specifications]. A bounding risk document, the TOCs, listing the overall TS system safety function would assessment was performed to justify the specifications in the plant TSs. Transferring still be available for the majority of proposed TS changes. This application control from the NRC to NextEra does not of LCO 3.0.9 is predicated upon the affect the operation, physical configuration, anticipated challenges. Therefore, the licensees performance of a risk or function of plant equipment or systems.

probability of an accident previously The proposed amendment does not impact evaluated is not significantly increased, assessment and the management of the initiators or assumptions of analyzed if at all. The consequences of an plant risk. The net change to the margin events, nor does it impact the mitigation of accident while relying on the allowance of safety is insignificant as indicated by accidents or transient events.

provided by proposed LCO 3.0.9 are no the anticipated low levels of associated Therefore, the proposed amendment does different than the consequences of an risk (ICCDP [incremental conditional not involve a significant increase in the accident while relying on the TS core damage probability] and ICLERP probability or consequences of an accident required actions in effect without the [incremental conditional large early previously evaluated.

allowance provided by proposed LCO release probability]) as shown in Table 2. Does the proposed amendment create 1 of Section 3.1.1 in the Safety the possibility of a new or different kind of 3.0.9. Therefore, the consequences of an accident from any accident previously accident previously evaluated are not Evaluation. Therefore, this change does evaluated?

significantly affected by this change. not involve a significant reduction in a Response: No.

The addition of a requirement to assess margin of safety. The proposed amendment is and manage the risk introduced by this The NRC staff has reviewed the administrative and does not alter plant change will further minimize possible analysis and, based on this review, it configuration, require installation of new concerns. Therefore, this change does appears that the three standards of 10 equipment, alter assumptions about not involve a significant increase in the CFR 50.92(c) are satisfied. Therefore, the previously analyzed accidents, or impact probability or consequences of an NRC staff proposes to determine that the operation or function of plant equipment or amendment request involves no systems.

accident previously evaluated.

Therefore, this proposed amendment does significant hazards consideration. not create the possibility of a new or different Criterion 2The Proposed Change Does Attorney for licensee: Joseph A. kind of accident from any accident Not Create the Possibility of a New or Aluise, Associate General Council previously evaluated.

Different Kind of Accident From any Nuclear, Entergy Services, Inc., 639 3. Does the proposed amendment involve Previously Evaluated Loyola Avenue, New Orleans, Louisiana a significant reduction in a margin of safety?

The proposed change does not 70113. Response: No.

involve a physical alteration of the plant NRC Branch Chief: Michael T. The proposed amendment is (no new or different type of equipment Markley. administrative. The TOCs is not required by will be installed). Allowing delay times regulation to be in the TSs. Removal does not for entering supported system TS when NextEra Energy Point Beach, LLC impact any safety assumptions or have the inoperability is due solely to an (NextEra, the Licensee), Docket Nos. potential to reduce a margin of safety. The 50-266 and 50-301, Point Beach proposed amendment involves a transfer of unavailable barrier, if risk is assessed control of the TOCs from the NRC to NextEra.

and managed, will not introduce new Nuclear Plant, Units 1 and 2, Town of Two Creeks, Manitowac County, No change in the technical content of the TSs failure modes or effects and will not, in is involved. Consequently, transfer from the the absence of other unrelated failures, Wisconsin NRC to NextEra has no impact on the margin lead to an accident whose consequences Date of amendment request: June 23, of safety.

exceed the consequences of accidents 2011. Therefore, the proposed amendment does previously evaluated. The addition of a Description of amendment request: not involve a significant reduction in a sroberts on DSK5SPTVN1PROD with NOTICES requirement to assess and manage the The proposed amendment will remove margin of safety.

risk introduced by this change will the Table of Contents from the The NRC staff has reviewed the further minimize possible concerns. Technical Specifications and place it licensees analysis and, based on this Thus, this change does not create the under licensee control. The Table of review, it appears that the three possibility of a new or different kind of Contents (TOCs) for the Technical standards of 10 CFR 50.92(c) are accident from an accident previously Specifications (TSs) is not being satisfied. Therefore, the NRC staff evaluated. eliminated. The responsibility for proposes to determine that the VerDate Mar<15>2010 16:12 Jul 25, 2011 Jkt 223001 PO 00000 Frm 00048 Fmt 4703 Sfmt 4703 E:\FR\FM\26JYN1.SGM 26JYN1

44618 Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices amendment request involves no DIWRB-2M and VIPRE-DIW-3 code/ standards of 50.92(c) are satisfied.

significant hazards consideration. correlation pairs to perform licensing Therefore, the NRC staff proposes to Attorney for licensee: William Blair, calculations of Westinghouse RFA-2 fuel in determine that the amendment request Senior Attorney, NextEra Energy Point North Anna cores will not result in a measurable impact on normal operating plant involves no significant hazards Beach, LLC, P.O. Box 14000, Juno releases and will not increase the predicted consideration.

Beach, FL 33408-0420. radiological consequences of accidents Attorney for licensee: Lillian M.

NRC Branch Chief: Robert J. postulated in the UFSAR [Updated Final Cuoco, Senior Counsel, Dominion Pascarelli. Safety Analysis Report]. Resources Services, Inc., 120 Tredegar Therefore, neither the probability of Street, RS-2, Richmond, VA 23219.

Virginia Electric and Power Company, occurrence nor the consequences of any NRC Branch Chief: Gloria Kulesa.

Docket Nos. 50-338 and 50-339, North accident previously evaluated is significantly Anna Power Station, Unit 1 and 2, increased. Previously Published Notices of Louisa County, Virginia 2. Does the change create the possibility of Consideration of Issuance of a new or different kind of accident from any Amendments to Facility Operating Date of amendment request: July 19, accident previously evaluated? Licenses, Proposed No Significant 2010, as supplemented September 9, Response: No.

2010, January 26, May 16, and June 23, Hazards Consideration Determination, The proposed change does not involve a 2011. physical alteration of the plant (no new or and Opportunity for a Hearing Description of amendment request: different type of equipment will be installed). The following notices were previously Changes are proposed to the Technical The use of VIPRE-D/WRB-2M and the published as separate individual Specifications to include an analytical VIPRE-D/W-3 code/correlation pairs and the notices. The notice content was the methodology for the critical heat flux applicable fuel design limits for DNBR does same as above. They were published as correlation. not impact any of the applicable design criteria and the licensing basis criteria will individual notices either because time Basis for proposed no significant did not allow the Commission to wait continue to be met. Demonstrated adherence hazards consideration determination: to these standards and criteria precludes new for this biweekly notice or because the As required by 10 CFR 50.91(a), the challenges to components and systems that action involved exigent circumstances.

licensee has provided its analysis of the could introduce a new type of accident. They are repeated here because the issue of no significant hazards Setpoint safety analysis evaluations have biweekly notice lists all amendments consideration, which is presented demonstrated that the use of VIPRE-D/WRB- issued or proposed to be issued below: 2M and VIPRE-D/W3 is acceptable. Design involving no significant hazards and performance criteria will continue to be

1. Does the change involve a significant met and no new single failure mechanisms consideration.

increase in the probability or consequences will be created. The use of the VIPRE-D/ For details, see the individual notice of an accident previously evaluated? WRB-2M and VIPRE-D/W-3 code/ in the Federal Register on the day and Response: No. correlation pairs and the Statistical DNBR page cited. This notice does not extend Approval of the proposed changes will Evaluation Methodology does not involve the notice period of the original notice.

allow Dominion to use the VIPRE [Versatile any alteration to plant equipment or Internals and Components Program for procedures that would introduce any new or Arizona Public Service Company, et al.,

ReactorsEPRI]-DIWRB-2M and VIPRE- unique operational modes or accident Docket Nos. STN 50-528, STN 50-529, DIW-3 code/correlation pairs to perform precursors. Thus, this change does not create and STN 50-530, Palo Verde Nuclear licensing calculations of Westinghouse RFA- the possibility of a new or different kind of Generating Station, Units 1, 2, and 3, 2 fuel in North Anna Cores, using the DDLs accident from any accident previously

[deterministic design limits] documented in Maricopa County, Arizona evaluated.

Appendix C of the DOM-NAF-2-A Fleet 3. Does this change involve a significant Date of amendment request: August Report and the SDL [statistical design limit] reduction in a margin of safety? 27, 2010, as supplemented by letters documented herein. Neither the code/ Response: No. dated February 11 and May 25, 2011.

correlation pair nor the Statistical Departure Approval of the proposed changes will Brief description of amendment from Nucleate Boiling Ratio (DNBR) allow Dominion to use the VIPRE-D/WRB- request: The proposed amendment Evaluation Methodology affect accident 2M and VIPRE-D/W-3 code/correlation pairs initiators and thus cannot increase the would revise the feedwater line break to perform licensing calculations of with loss of offsite power and single probability of any accident. Further, since Westinghouse RFA-2 fuel in North Anna both the deterministic and statistical DNBR failure (FWLB/LOP/SF) analysis cores, using the DDLs documented in limits meet the required design basis of Appendix C of the DOM-NAF-2-A Fleet summarized in the Palo Verde Nuclear avoiding Departure from Nucleate Boiling Report and the SDL documented herein. The Generating Station Updated Safety (DNB) with 95% probability at a 95% SDL has been developed in accordance with Analysis Report. The revision would confidence level, the use of the new code/ the Statistical DNBR Evaluation change the credited operator action to correlation and Statistical DNBR Evaluation Methodology. North Anna TS 2.1, Safety 20 minutes from 30 minutes to control Methodology do not increase the potential Limits, specifies that any DNBR limit consequences of any accident. Finally, the the pressurizer level. The revision established by any code/correlation must would also revise the rate of reactor full core DNB design limit provides increased provide at least 95% non-DNB probability at assurance that the consequences of a coolant pump (RCP) bleed-off to the a 95% confidence level. The DNBR limits postulated accident which includes meet the design basis of avoiding DNB with reactor drain tank from three gallons per radioactive release would be minimized 95% probability at a 95% confidence level. minute to zero.

because the overall number of rods in DNB The required DNBR margin of safety for Date of publication of individual would not exceed the 0.1% level. The North Anna Power Station, which in this notice in Federal Register: June 28, pertinent evaluations to be performed as part case is the margin between the 95/95 DNBR 2011 (76 FR 37853).

of the cycle specific reload safety analysis to limit and clad failure, is therefore not Expiration date of individual notice:

sroberts on DSK5SPTVN1PROD with NOTICES confirm that the existing safety analyses reduced.

remain applicable have been performed and July 28, 2011, for comments and August Therefore, the proposed TS change does 29, 2011, for hearings.

determined to be acceptable. The use of a not involve a significant reduction in a different code/correlation pair will not margin of safety. Notice of Issuance of Amendments to increase the probability of an accident Facility Operating Licenses because plant systems will not be operated in The NRC staff has reviewed the a different manner, and system interfaces licensees analysis and, based on this During the period since publication of will not change. The use of the VIPRE- review, it appears that the three the last biweekly notice, the VerDate Mar<15>2010 16:12 Jul 25, 2011 Jkt 223001 PO 00000 Frm 00049 Fmt 4703 Sfmt 4703 E:\FR\FM\26JYN1.SGM 26JYN1

Federal Register / Vol. 76, No. 143 / Tuesday, July 26, 2011 / Notices 44619 Commission has issued the following Brief description of amendment: The This Confirmatory Order is the result amendments. The Commission has license amendments revise Technical of an agreement reached during an determined for each of these Specifications (TS) Section 3.4.12, Low alternative dispute resolution (ADR) amendments that the application Temperature Overpressure Protection mediation session conducted on May complies with the standards and (LTOP) System, to correct an 25, 2011, at the NRC Region IV offices requirements of the Atomic Energy Act inconsistency between the TS, and in Arlington, Texas.

of 1954, as amended (the Act), and the implementation of procedures and II Commissions rules and regulations. administrative controls for Safety The Commission has made appropriate Injection pumps required to mitigate a On January 27, 2010, the NRC findings as required by the Act and the postulated loss of decay heat removal conducted a routine unannounced Commissions rules and regulations in during mid-loop operation as discussed inspection of the Bozeman Deaconess 10 CFR Chapter I, which are set forth in in NRC Generic Letter 88-17, Loss of Hospital facility to evaluate radiation the license amendment. Decay Heat Removal. safety and security, as well as Notice of Consideration of Issuance of Date of issuance: June 29, 2011. compliance with Commission rules and Amendment to Facility Operating Effective date: As of the date of regulations and the conditions of the License, Proposed No Significant issuance and shall be implemented license. During the inspection, it was Hazards Consideration Determination, within 60 days. determined that an employee of and Opportunity for A Hearing in Amendment Nos.: 167, 167, 174, 174. Bozeman Deaconess Hospital failed to connection with these actions was Facility Operating License Nos. NPF- secure radioactive materials from published in the Federal Register as 72, NPF-77, NPF-37, and NPF-66: The unauthorized access or removal from amendments revise the TSs and license. the facilitys nuclear medicine indicated.

Date of initial notice in Federal laboratory (hot lab). On March 8, 2010, Unless otherwise indicated, the the NRC Office of Investigations (OI),

Commission has determined that these Register: October 5, 2010 (75 FR 61526).

The August 24, 2010, and January 13, Region IV, began an investigation (OI amendments satisfy the criteria for Case No. 4-2010-033) to determine categorical exclusion in accordance 2011, supplements contained clarifying information and did not change the NRC whether employees from Bozeman with 10 CFR 51.22. Therefore, pursuant Deaconess Hospital willfully failed to to 10 CFR 51.22(b), no environmental staffs initial proposed finding of no significant hazards consideration. secure radioactive material during impact statement or environmental periods when authorized personnel assessment need be prepared for these The Commissions related evaluation of the amendments is contained in a were absent from the hot lab. Based on amendments. If the Commission has the results of the inspection and the prepared an environmental assessment safety evaluation dated June 29, 2011.

No significant hazards consideration evidence developed during the under the special circumstances investigation, the NRC identified two provision in 10 CFR 51.22(b) and has comments received: No.

apparent violations. The first apparent made a determination based on that Dated at Rockville, Maryland, this 15th day violation involved a willful failure to assessment, it is so indicated. of July 2011.

secure licensed materials from For further details with respect to the For the Nuclear Regulatory Commission.

unauthorized removal or access as action see (1) The applications for Joseph G. Giitter, required by 10 CFR 20.1801. The second amendment, (2) the amendment, and (3) Director, Division of Operating Reactor violation involved a failure to control the Commissions related letter, Safety Licensing, Office of Nuclear Reactor and maintain constant surveillance of Evaluation and/or Environmental Regulation. licensed material as required by 10 CFR Assessment as indicated. All of these [FR Doc. 2011-18525 Filed 7-25-11; 8:45 am] 20.1802.

items are available for public inspection BILLING CODE 7590-01-P By letter dated April 12, 2011, the at the NRCs Public Document Room NRC transmitted the results of the (PDR), located at One White Flint North, inspection and a factual summary of Room O1-F21, 11555 Rockville Pike NUCLEAR REGULATORY OIs Investigation Report 4-2010-033 to (first floor), Rockville, Maryland 20852. COMMISSION Bozeman Deaconess Hospital. In the Publicly available documents created or [ Docket No. 030-33305; License No. 25- April 12 letter, the NRC informed the received at the NRC are accessible 10994-04; EA-10-258; NRC-2011-0163] Licensee that the NRC was considering electronically through the Agencywide escalated enforcement action for the Documents Access and Management In the Matter of Bozeman Deaconess apparent violations. The NRC offered System (ADAMS) in the NRC Library at Foundation, dba Bozeman Deaconess the Licensee the opportunity to request http://www.nrc.gov/reading-rm/ Hospital, Bozeman, MT; Confirmatory a predecisional enforcement conference adams.html. If you do not have access Order Modifying License; (Effective or request ADR with the NRC in an to ADAMS or if there are problems in Immediately) attempt to resolve issues associated with accessing the documents located in this matter. In response, on April 21, ADAMS, contact the PDR Reference I 2011, Bozeman Deaconess Hospital staff at 1-800-397-4209, 301-415-4737 Bozeman Deaconess Hospital requested ADR to resolve this matter or by email to pdr.resource@nrc.gov. (Licensee) is the holder of Materials with the NRC.

License No. 25-10994-04 issued by the On May 25, 2011, the NRC and Exelon Generation Company, LLC, Nuclear Regulatory Commission (NRC Licensee representatives met in an ADR Docket Nos. STN 50-456 and STN 50-or the Commission) pursuant to Title 10 session with a professional mediator, sroberts on DSK5SPTVN1PROD with NOTICES 457, Braidwood Station, Units 1 and 2, of the Code of Federal Regulations (10 arranged through the Cornell University Will County, Illinois; Docket Nos. STN CFR) parts 30 and 35. The license Institute on Conflict Resolution. ADR is 50-454 and STN 50-455, Byron Station, authorizes the operation of the a process in which a neutral mediator Unit 1 and 2, Ogle County, Illinois Licensees facility in accordance with with no decision-making authority Date of application for amendment: the conditions specified therein, at 915 assists the parties in reaching an June 29, 2010, as supplemented on Highland Boulevard, Bozeman, agreement on resolving any differences August 24, 2010, and January 13, 2011. Montana. regarding the dispute. This VerDate Mar<15>2010 16:12 Jul 25, 2011 Jkt 223001 PO 00000 Frm 00050 Fmt 4703 Sfmt 4703 E:\FR\FM\26JYN1.SGM 26JYN1