Biweekly Notice; Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations, 38094-38099 [2012-15176]
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38094
Federal Register / Vol. 77, No. 123 / Tuesday, June 26, 2012 / Notices
B. Reports.
1. Introductory Remarks.
2. Panel Presentation with Dr. Jeffrey
Bolster, Associate Professor at the
University of New Hampshire, and
Gregory White, Qualified Member of the
Engine Department—Oiler, on ‘‘The
Story of Black Jacks: African American
Seamen in the Age of Sail and a
Washington Prisoner.’’
3. Presentation by Judith Havemann,
Director of the NEH Office of
Communications, on ‘‘Nine Things You
Need to Know about the New NEH Web
site.’’
4. Staff Report.
5. Congressional Report.
6. Reports on Policy and General
Matters.
a. Challenge Grants & Federal/State
Partnership.
b. Digital Humanities.
c. Education Programs.
d. Preservation and Access.
e. Public Programs.
f. Research Programs.
g. Jefferson Lecture/National
Humanities Medals.
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The remainder of the Plenary Session
will be for consideration of specific
applications and Jefferson Lecture and
National Humanities Medal candidates,
and therefore will be closed to the
public.
As identified above, portions of the
meeting of the National Council on the
Humanities will be closed to the public
pursuant to sections 552b(c)(4),
552b(c)(6) and 552b(c)(9)(b) of Title 5,
U.S.C., as amended. The closed sessions
will include review of personal and/or
proprietary financial and commercial
information given in confidence to the
agency by grant applicants, and
discussion of certain information, the
premature disclosure of which could
significantly frustrate implementation of
proposed agency action. I have made
this determination pursuant to the
authority granted me by the Chairman’s
Delegation of Authority to Close
Advisory Committee Meetings dated
July 19, 1993.
I. Accessing Information and
Submitting Comments
NUCLEAR REGULATORY
COMMISSION
A. Accessing Information
[NRC–2012–0143]
Biweekly Notice; Applications and
Amendments to Facility Operating
Licenses and Combined Licenses
Involving No Significant Hazards
Considerations
Background
Pursuant to Section 189a.(2) of the
Atomic Energy Act of 1954, as amended
(the Act), the U.S. Nuclear Regulatory
Commission (the Commission or NRC)
is publishing this regular biweekly
notice. The Act requires the
Commission publish notice of any
amendments issued, or proposed to be
issued and grants the Commission the
authority to issue and make
immediately effective any amendment
to an operating license or combined
license, as applicable, 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 May 31,
2012 to June 27, 2012. The last biweekly
notice was published on June 12, 2012
(77 FR 35069).
You may access information
and comment submissions related to
this document, which the NRC
possesses and are publicly available, by
searching on https://www.regulations.gov
under Docket ID NRC–2012–0143. You
may submit comments by the following
methods:
• Federal Rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0143. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–492–3668;
email: Carol.Gallagher@nrc.gov.
• Mail comments to: Cindy Bladey,
Chief, Rules, Announcements, and
Directives Branch (RADB), Office of
Administration, Mail Stop: TWB–05–
B01M, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001.
• Fax comments to: RADB at 301–
492–3446.
For additional direction on accessing
information and submitting comments,
see ‘‘Accessing Information and
Submitting Comments’’ in the
SUPPLEMENTARY INFORMATION section of
this document.
Please refer to Docket ID NRC–2012–
0143 when contacting the NRC about
the availability of information regarding
this document. You may access
information related to this document,
which the NRC possesses and is
publicly available, by the following
methods:
• Federal Rulemaking Web Site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2012–0143.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publicly
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/adams.html. To begin the search,
select ‘‘ADAMS Public Documents’’ and
then select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov.
Documents may be viewed in ADAMS
by performing a search on the document
date and docket number.
• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
[FR Doc. 2012–15533 Filed 6–25–12; 8:45 am]
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B. Submitting Comments
SUPPLEMENTARY INFORMATION:
Dated: June 21, 2012.
Lisette Voyatzis,
Committee Management Officer.
ADDRESSES:
Please include Docket ID NRC–2012–
0143 in the subject line of your
comment submission, in order to ensure
that the NRC is able to make your
comment submission available to the
public in this docket.
The NRC cautions you not to include
identifying or contact information in
comment submissions that you do not
want to be publicly disclosed. The NRC
posts all comment submissions at https://
www.regulations.gov as well as entering
the comment submissions into ADAMS,
and the NRC does not edit comment
submissions to remove identifying or
contact information.
If you are requesting or aggregating
comments from other persons for
submission to the NRC, then you should
inform those persons not to include
identifying or contact information in
their comment submissions that they do
not want to be publicly disclosed. Your
request should state that the NRC will
not edit comment submissions to
remove such information before making
the comment submissions available to
the public or entering the comment
submissions into ADAMS.
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Federal Register / Vol. 77, No. 123 / Tuesday, June 26, 2012 / Notices
Notice of Consideration of Issuance of
Amendments to Facility Operating
Licenses and Combined 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
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 or
combined license. Requests for a
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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. The NRC
regulations are accessible electronically
from the NRC Library on the NRC’s Web
site at https://www.nrc.gov/reading-rm/
doc-collections/cfr/. If a request for a
hearing or petition for leave to intervene
is filed by the above date, the
Commission or a presiding officer
designated by the Commission or by the
Chief Administrative Judge of the
Atomic Safety and Licensing Board
Panel, will rule on the request and/or
petition; and the Secretary or the Chief
Administrative Judge of the Atomic
Safety and Licensing Board will issue a
notice of a hearing or an appropriate
order.
As required by 10 CFR 2.309, a
petition for leave to intervene shall set
forth with particularity the interest of
the petitioner in the proceeding, and
how that interest may be affected by the
results of the proceeding. The petition
should specifically explain the reasons
why intervention should be permitted
with particular reference to the
following general requirements: (1) The
name, address, and telephone number of
the requestor or petitioner; (2) the
nature of the requestor’s/petitioner’s
right under the Act to be made a party
to the proceeding; (3) the nature and
extent of the requestor’s/petitioner’s
property, financial, or other interest in
the proceeding; and 4) the possible
effect of any decision or order which
may be entered in the proceeding on the
requestor’s/petitioner’s interest. The
petition must also identify the specific
contentions which the requestor/
petitioner seeks to have litigated at the
proceeding.
Each contention must consist of a
specific statement of the issue of law or
fact to be raised or controverted. In
addition, the requestor/petitioner shall
provide a brief explanation of the bases
for the contention and a concise
statement of the alleged facts or expert
opinion which support the contention
and on which the requestor/petitioner
intends to rely in proving the contention
at the hearing. The requestor/petitioner
must also provide references to those
specific sources and documents of
which the petitioner is aware and on
which the requestor/petitioner intends
to rely to establish those facts or expert
opinion. The petition must include
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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 the 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 EFiling 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 email 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
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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 NRCissued 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 the
NRC’s public Web site at https://
www.nrc.gov/site-help/e-submittals/
apply-certificates.html. System
requirements for accessing the ESubmittal server are detailed in the
NRC’s ‘‘Guidance for Electronic
Submission,’’ which is available on the
agency’s public Web site at https://
www.nrc.gov/site-help/esubmittals.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’s Web
site. Further information on the Webbased submission form, including the
installation of the Web browser plug-in,
is available on the NRC’s public Web
site at https://www.nrc.gov/site-help/esubmittals.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 the NRC
guidance available on the NRC’s public
Web site at https://www.nrc.gov/sitehelp/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 EFiling system time-stamps the document
and sends the submitter an email notice
confirming receipt of the document. The
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E-Filing system also distributes an email
notice that provides access to the
document to the NRC’s 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’s Web site at https://
www.nrc.gov/site-help/esubmittals.html, by email at
MSHD.Resource@nrc.gov, or by a tollfree 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 firstclass 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 the NRC’s
electronic hearing docket which is
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available to the public at https://
ehd1.nrc.gov/ehd/, unless excluded
pursuant to an order of the Commission,
or the presiding officer. Participants are
requested not to include personal
privacy information, such as social
security numbers, home addresses, or
home phone numbers in their filings,
unless an NRC regulation or other law
requires submission of such
information. With respect to
copyrighted works, except for limited
excerpts that serve the purpose of the
adjudicatory filings and would
constitute a Fair Use application,
participants are requested not to include
copyrighted materials in their
submission.
Petitions for leave to intervene must
be filed no later than 60 days from the
date of publication of this notice. Nontimely 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 online in the NRC Library at
https://www.nrc.gov/reading-rm/
adams.html. Persons who do not have
access to ADAMS or who encounter
problems in accessing the documents
located in ADAMS, should contact the
NRC’s PDR Reference staff at 1–800–
397–4209, 301–415–4737, or by email to
pdr.resource@nrc.gov.
Northern States Power Company—
Minnesota, Docket No. 50–263,
Monticello Nuclear Generating Plant,
Wright County, Minnesota
Date of amendment request: May 25,
2012.
Description of amendment request:
The licensee proposed to revise the
licensing basis regarding the time delay
assumed in the safety analyses for the
degraded voltage transfer logic
associated with the 1AR Transformer,
which is governed by Technical
Specifications 3.3.8.1, ‘‘Loss of Power
(LOP) Instrumentation.’’ Specifically,
the revision will remove the capability
to automatically transfer to the 1AR
Transformer as a source of power to the
essential buses on degraded voltage and
instead directly transfer to the
Emergency Diesel Generators (EDGs).
This transfer will ensure that Class 1E
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equipment is capable of performing its
function to meet the requirements of the
current licensing basis.
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 (NSHC) analysis. The
NRC staff reviewed the licensee’s NSHC
analysis and has prepared its own as
follows:
1. Does the proposed amendment involve
a significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
The proposed amendment does not affect
any previously used accident initiators or
precursors, and does not change the initial
conditions contributing to the severity or
consequences of previously analyzed
accidents or malfunctions. The power
transfer scheme was not a precursor of
previously analyzed accidents, and took no
part in determining the consequences of
previously analyzed accidents. As a result,
all previous safety analyses will continue to
meet all applicable acceptance criteria since
the proposed amendment will not degrade
the performance of structures, systems, and
components (SSCs) important to safety.
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.
No new accident scenarios, precursors,
failure mechanisms, or limiting single
failures will be introduced as a result of the
proposed amendment. The proposed revision
of the degraded voltage transfer logic scheme
(i.e., to transfer directly to the EDG instead
of first attempting to transfer to the IAR
Transformer) was previously licensed for
Monticello, and is typical for the industry.
The delay time associated with the degraded
voltage transfer logic was not postulated as
an initiator of any previously analyzed
accident, and is not expected to create any
new system interactions or failure modes of
any SSCs. Thus, equipment important to
safety will continue to operate as designed,
and the proposed change will not result in
any adverse conditions or any increase in
challenges to safety systems.
Therefore, operation of the plant in
accordance with the proposed amendment
will not create the possibility of a new or
different type 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 aims to correct
non-conservative values assumed in the
analyses for the degraded voltage protection
function. The proposed amendment assures
that the design requirements of the
emergency electrical power system will
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continue to be met. The proposed
amendment does not affect previously used
safety acceptance criteria, assumptions,
scenarios, and analysis methodology.
Therefore, the proposed amendment does
not involve any reduction in a margin of
safety.
The NRC staff has reviewed the
licensee’s analysis and, based on its
own analysis, concludes that the three
standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff
proposes to determine that the proposed
amendment involves no significant
hazards consideration.
Attorney for the licensee: Peter M.
Glass, Assistant General Counsel, Xcel
Energy Services, Inc., 414 Nicollet Mall,
Minneapolis, MN 55401.
NRC Branch Chief: Istvan Frankl,
Acting.
Union Electric Company, Docket No.
50–483, Callaway Plant, Unit 1,
Callaway County, Missouri
Date of amendment request:
September 22, 2011.
Description of amendment request:
The amendment would revise Required
Action B.1 of Technical Specification
(TS) 3.3.6, ‘‘Containment Purge Isolation
Instrumentation,’’ such that a Note
would be added to the Required Action
to conditionally allow containment
mini-purge supply and exhaust valves
that have been closed in accordance
with the Action to be opened under
administrative controls as required for
certain operational needs. The proposed
change is similar to allowances already
in place in TS 3.6.3, ‘‘Containment
Isolation Valves,’’ and TS 3.9.4,
‘‘Containment Penetrations.’’
Basis for proposed no significant
hazards consideration determination:
As required by 10 CFR 50.91(a), the
licensee has provided its analysis of the
issue of no significant hazards
consideration, which is presented
below:
1. Does the proposed change involve a
significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
Overall protection system performance will
remain within the bounds of the previously
performed accident analyses since there are
no design changes. All design, material, and
construction standards that were applicable
prior to this amendment request will be
maintained. There will be no changes to any
design or operating limits.
The proposed change does not involve or
result in any changes to accident initiators or
precursors, nor does it alter the design
assumptions or conditions of the plant. The
proposed change for the mini-purge valves
which support the mitigation of certain
accidents would not affect the initiation of
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those accidents and therefore does not affect
the probability of occurrence of an accident.
Per the provisions of the proposed Note for
Required Action B.1 of TS 3.3.6, the
automatic containment isolation function(s)
associated with a Phase A containment
isolation signal (which is the trip function/
signal credited in the accident analysis)
would continue to be required Operable. At
the same time, the proposed change helps to
support venting of containment to ensure the
initial condition assumptions for
containment pressure in the accident
analyses are met during a TS-allowed period
of radiation monitor inoperability. There are
no design changes to the containment minipurge isolation valves or the associated
actuation circuitry. There will be no changes
to the operation of these valves other than the
limited durations during which they may be
open under administrative controls with
inoperable actuation instrumentation (i.e.
while a TS Required Action is in effect).
Exceptions to Technical Specification
requirements are allowed in situations where
plant operation would otherwise be restricted
in a manner that is not commensurate with
the desired safety objective, especially when
those exceptions are of short duration and are
accompanied by compensatory measures.
Therefore, the proposed change will not alter
or prevent the capability of structures,
systems, and components (SSCs) to perform
their intended functions for mitigating the
consequences of an accident as assumed in
the accident analysis.
The proposed change does not physically
alter the design of any safety-related systems,
nor does it affect the way in which safetyrelated systems are assumed to perform their
functions.
The proposed change will not affect the
source term, containment isolation, or
radiological release assumptions used in
evaluating the radiological consequences of
an accident previously evaluated. The
applicable radiological dose criteria will
continue to be met.
Therefore, the proposed change does not
involve a significant increase in the
probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the
possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No.
There are no proposed design changes, nor
are there any changes in the method by
which any safety-related plant structure,
system, or component (SSC) is assumed to
perform its specified safety function. The
proposed change will not affect the normal
method of plant operation or change any
operating parameters. Equipment
performance necessary to fulfill safety
analysis missions will be unaffected. The
proposed change will not alter any
assumptions required to meet the safety
analysis acceptance criteria. No new accident
scenarios, transient precursors, failure
mechanisms, or limiting single failures will
be introduced as a result of this amendment.
There will be no adverse effect or challenges
imposed on any safety-related system as a
result of this amendment.
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Federal Register / Vol. 77, No. 123 / Tuesday, June 26, 2012 / Notices
The proposed amendment will not alter the
design or performance of the 7300 Process
Protection System, Nuclear Instrumentation
System, or Solid State Protection System
used in the plant protection systems.
The proposed change does not, therefore,
create the possibility of a new or different
accident from any accident previously
evaluated.
3. Does the proposed change involve a
significant reduction in a margin of safety?
Response: No.
There will be no effect on those plant
systems necessary to assure the
accomplishment of protection functions.
There will be no impact on the overpower
limit, departure from nucleate boiling ratio
(DNBR) limits, heat flux hot channel factor
(FQ), nuclear enthalpy rise hot channel factor
(FDH), loss of coolant accident peak cladding
temperature (LOCA PCT), peak local power
density, or any other margin of safety. Modespecific required shutdown margins in the
COLR [Core Operating Limits Report] will
not be changed. The applicable radiological
dose consequence acceptance criteria will
continue to be met. The proposed changes do
not alter the design of the containment minipurge system or the supporting
instrumentation. As containment is a
principal safety barrier to the release of
radioactivity to the environment for
postulated design basis accidents, there will
be continued assurance that the containment
mini-purge isolation system will perform its
intended function of supporting containment
such that the assumptions in the accident
analyses remain valid.
The proposed change does not eliminate
any surveillances or alter the frequency of
surveillances required by the Technical
Specifications. None of the acceptance
criteria for any accident analysis will be
changed.
Therefore, the proposed change does not
involve a significant reduction in a margin of
safety.
rmajette on DSK2TPTVN1PROD with NOTICES
The NRC staff has reviewed the
licensee’s analysis and, based on this
review, it appears that the three
standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff
proposes to determine that the
amendment request involves no
significant hazards consideration.
Attorney for licensee: John O’Neill,
Esq., Pillsbury Winthrop Shaw Pittman
LLP, 2300 N Street NW., Washington,
DC 20037.
NRC Branch Chief: Michael T.
Markley.
Notice of Issuance of Amendments to
Facility Operating Licenses and
Combined Licenses
During the period since publication of
the last biweekly notice, the
Commission has issued the following
amendments. The Commission has
determined for each of these
amendments that the application
complies with the standards and
requirements of the Atomic Energy Act
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15:33 Jun 25, 2012
Jkt 226001
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.
A notice of consideration of issuance
of amendment to facility operating
license or combined license, as
applicable, 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 online in the NRC Library
at https://www.nrc.gov/reading-rm/
adams.html. If you do not have access
to ADAMS or if there are problems in
accessing the documents located in
ADAMS, contact the PDR’s Reference
staff at 1–800–397–4209, 301–415–4737
or by email to pdr.resource@nrc.gov.
Carolina Power and Light Company, et
al., Docket No. 50–400, Shearon Harris
Nuclear Power Plant, Unit 1, Wake and
Chatham Counties, North Carolina
Date of amendment request: August
22, 2011, as supplemented by letter
dated February 23, March 20, and April
2, 2012.
Description of amendment request:
The amendment revised Technical
Specification (TS) 6.9.1.6, ‘‘Core
Operating Limits Report,’’ to add plantspecific methodology, ANP–3011 (P),
‘‘Harris Nuclear Plant Unit 1 Realistic
Large Break LOCA [loss-of-coolant
accident] Analysis,’’ Revision 1, that
implements AREVA’s NRC-approved
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topical report, EMF–2103(P)(A),
‘‘Realistic Large Break LOCA
Methodology for Pressurized Water
Reactors’’ Revision 0.
Date of issuance: May 30, 2012.
Effective date: As of the date of
issuance and shall be implemented
within 60 days of issuance.
Amendment No.: 138.
Renewed Facility Operating License
No. NPF–63: The amendment revised
the TSs and the Facility Operating
License.
Date of initial notice in Federal
Register: January 10, 2012 (77 FR
1516). The February 23, March 20, and
April 2, 2012, supplements provided
additional information that clarified the
application, did not expand the scope of
the application as originally noticed,
and did not change the NRC staff’s
initial proposed no significant hazards
consideration determination.
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated May 30, 2012.
No significant hazards consideration
comments received: No.
NRC Branch Chief: Douglas A.
Broaddus.
Carolina Power and Light Company, et
al., Docket No. 50–400, Shearon Harris
Nuclear Power Plant, Unit 1, Wake and
Chatham Counties, North Carolina
Date of application for amendment:
April 28, 2011, as supplemented by
letters dated June 23,August 3, August
15, August 25, August 30, August 31,
September 6, September 7, October
20,October 21, October 28, November
28, December 20, 2011, February 9, and
March 26, 2012.
Brief description of amendment: The
amendment increases the rated thermal
power (RTP)level from 2900 megawatts
thermal (MWt) to 2948 MWt, and makes
technical specification changes as
necessary to support operation at the
uprated power level. The change is an
increase in RTP of approximately 1.66
percent. The power uprate is
characterized as a measurement
uncertainty recapture using the
Cameron Leading Edge Flow Meter
CheckPlusSystem to improve plant
calorimetric heat balance measurement
accuracy.
Date of issuance: May 30, 2012.
Effective date: As of the date of
issuance and shall be implemented
within 120 days of issuance.
Amendment No.: 139.
Renewed Facility Operating License
No. NPF–63: Amendment revises the
Technical Specifications.
Date of initial notice in Federal
Register: September 13, 2011 (76 FR
56486). The June 23, August 3, August
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15, August 25, August 30, August 31,
September 6, September 7, October 20,
October 21, October 28, November 28,
December 20, 2011, February 9, and
March 26, 2012, supplements provided
additional information that clarified the
application, did not expand the scope of
the application as originally noticed and
did not change the NRC staff’s initial
proposed no significant hazards
consideration determination.
The Commission’s related evaluation
of the amendment is contained in a
safety evaluation dated May 30, 2012.
No significant hazards consideration
comments received: No.
rmajette on DSK2TPTVN1PROD with NOTICES
NextEra Energy Duane Arnold, LLC,
Docket No. 50–331, Duane Arnold
Energy Center (DAEC), Linn County,
Iowa
Date of application for amendment:
May 31, 2011, as supplemented by
letters dated March 16, 2012, and April
5, 2012.
Brief description of amendment: The
amendment upgrades DAEC Emergency
Action Levels based on Nuclear Energy
Institute (NEI) 99–01, Revision 5,
‘‘Methodology for Development of
Emergency Action Levels,’’ using the
guidance of NRC Regulatory Issue
Summary 2003–18, Supplement 2, ‘‘Use
of Nuclear Energy Institute (NEI) 99–01,
‘‘Methodology for Development of
Emergency Action Levels.’’
Date of issuance: June 1, 2012.
Effective date: As of the date of
issuance and shall be implemented
within 120 days.
Amendment No.: 281.
Renewed Facility Operating License
No. DPR–49: The amendment revised
the Duane Arnold Energy Center
Emergency Plan.
Date of initial notice in Federal
Register: November 15, 2011 (76 FR
70774).
The supplemental information dated
March 16, 2012, and April 5, 2012
contained clarifying information, did
not change the scope of the May 31,
2011, application on the initial no
significant hazards consideration
determination, and did not expand the
scope of the original Federal Register
notice.
The Commission’s related evaluation
of the amendment is contained in a
Safety Evaluation dated June 1, 2012.
No significant hazards consideration
comments received: No.
For the Nuclear Regulatory Commission.
VerDate Mar<15>2010
15:33 Jun 25, 2012
Jkt 226001
Dated at Rockville, Maryland, this 14th day
of June 2012.
A. Louise Lund,
Deputy Director, Division of Operating
Reactor Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2012–15176 Filed 6–25–12; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS) Meeting of the
ACRS Subcommittee on Radiation
Protection and Nuclear Materials;
Notice of Meeting
The ACRS Subcommittee on
Radiation Protection and Nuclear
Materials will hold a meeting on July
10, 2012, Room T–2B1, 11545 Rockville
Pike, Rockville, Maryland.
The entire meeting will be open to
public attendance.
The agenda for the subject meeting
shall be as follows:
Tuesday, July 10, 2012—8:30 a.m. Until
12 p.m.
The Subcommittee will review
Revision 3 of ISG–8, ‘‘Burnup Credit in
the Criticality Safety Analyses of PWR
Spent Fuel in Transport and Storage
Casks.’’ The Subcommittee will hear
presentations by and hold discussions
with the NRC staff and other interested
persons regarding this matter. The
Subcommittee will gather information,
analyze relevant issues and facts, and
formulate proposed positions and
actions, as appropriate, for deliberation
by the Full Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official (DFO), Christopher
Brown (Telephone 301–415–7111 or
Email: Christopher.Brown@nrc.gov) five
days prior to the meeting, if possible, so
that appropriate arrangements can be
made. Thirty-five hard copies of each
presentation or handout should be
provided to the DFO thirty minutes
before the meeting. In addition, one
electronic copy of each presentation
should be emailed to the DFO one day
before the meeting. If an electronic copy
cannot be provided within this
timeframe, presenters should provide
the DFO with a CD containing each
presentation at least thirty minutes
before the meeting. Electronic
recordings will be permitted only
during those portions of the meeting
that are open to the public. Detailed
procedures for the conduct of and
participation in ACRS meetings were
PO 00000
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38099
published in the Federal Register on
October 17, 2011, (76 FR 64126–64127).
Detailed meeting agendas and meeting
transcripts are available on the NRC
Web site at https://www.nrc.gov/readingrm/doc-collections/acrs. Information
regarding topics to be discussed,
changes to the agenda, whether the
meeting has been canceled or
rescheduled, and the time allotted to
present oral statements can be obtained
from the Web site cited above or by
contacting the identified DFO.
Moreover, in view of the possibility that
the schedule for ACRS meetings may be
adjusted by the Chairman as necessary
to facilitate the conduct of the meeting,
persons planning to attend should check
with these references if such
rescheduling would result in a major
inconvenience.
If attending this meeting, please enter
through the One White Flint North
building, 11555 Rockville Pike,
Rockville, MD. After registering with
security, please contact Mr. Theron
Brown (240–888–9835) to be escorted to
the meeting room.
Dated: June 18, 2012.
Antonio Dias,
Technical Advisor, Advisory Committee on
Reactor Safeguards.
[FR Doc. 2012–15524 Filed 6–25–12; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS); Meeting of the
ACRS Subcommittee on U.S.
Advanced Pressurized Power Reactor
Revision to the June 19, 2012, ACRS
Meeting Federal Register Notice
The Federal Register Notice for the
ACRS Subcommittee Meeting on US–
APWR scheduled to be held on July 9,
2012, is being revised to notify the
following:
The entire meeting will be open to
public attendance, with the exception of
a portion that may be closed to protect
information that is proprietary pursuant
to 5 U.S.C. 552b(c)(4).
The notice of this meeting was
previously published in the Federal
Register on Tuesday, June 19, 2012 [77
FR 36581–36582].
Further information regarding this
meeting can be obtained by contacting
Mr. Girija Shukla, Designated Federal
Official (Telephone: 301–415–6855,
Email: Girija.Shukla@nrc.gov) between
8:15 a.m. and 5 p.m. (ET).
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Agencies
[Federal Register Volume 77, Number 123 (Tuesday, June 26, 2012)]
[Notices]
[Pages 38094-38099]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-15176]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0143]
Biweekly Notice; Applications and Amendments to Facility
Operating Licenses and Combined Licenses Involving No Significant
Hazards Considerations
Background
Pursuant to Section 189a.(2) of the Atomic Energy Act of 1954, as
amended (the Act), the U.S. Nuclear Regulatory Commission (the
Commission or NRC) is publishing this regular biweekly notice. The Act
requires the Commission publish notice of any amendments issued, or
proposed to be issued and grants the Commission the authority to issue
and make immediately effective any amendment to an operating license or
combined license, as applicable, 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 May 31, 2012 to June 27, 2012. The last
biweekly notice was published on June 12, 2012 (77 FR 35069).
ADDRESSES: You may access information and comment submissions related
to this document, which the NRC possesses and are publicly available,
by searching on https://www.regulations.gov under Docket ID NRC-2012-
0143. You may submit comments by the following methods:
Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0143. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
Mail comments to: Cindy Bladey, Chief, Rules,
Announcements, and Directives Branch (RADB), Office of Administration,
Mail Stop: TWB-05-B01M, U.S. Nuclear Regulatory Commission, Washington,
DC 20555-0001.
Fax comments to: RADB at 301-492-3446.
For additional direction on accessing information and submitting
comments, see ``Accessing Information and Submitting Comments'' in the
SUPPLEMENTARY INFORMATION section of this document.
SUPPLEMENTARY INFORMATION:
I. Accessing Information and Submitting Comments
A. Accessing Information
Please refer to Docket ID NRC-2012-0143 when contacting the NRC
about the availability of information regarding this document. You may
access information related to this document, which the NRC possesses
and is publicly available, by the following methods:
Federal Rulemaking Web Site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0143.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to pdr.resource@nrc.gov. Documents may be viewed in
ADAMS by performing a search on the document date and docket number.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
B. Submitting Comments
Please include Docket ID NRC-2012-0143 in the subject line of your
comment submission, in order to ensure that the NRC is able to make
your comment submission available to the public in this docket.
The NRC cautions you not to include identifying or contact
information in comment submissions that you do not want to be publicly
disclosed. The NRC posts all comment submissions at https://www.regulations.gov as well as entering the comment submissions into
ADAMS, and the NRC does not edit comment submissions to remove
identifying or contact information.
If you are requesting or aggregating comments from other persons
for submission to the NRC, then you should inform those persons not to
include identifying or contact information in their comment submissions
that they do not want to be publicly disclosed. Your request should
state that the NRC will not edit comment submissions to remove such
information before making the comment submissions available to the
public or entering the comment submissions into ADAMS.
[[Page 38095]]
Notice of Consideration of Issuance of Amendments to Facility Operating
Licenses and Combined 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 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 or
combined 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. The NRC regulations are accessible electronically from the NRC
Library on the NRC's Web site at https://www.nrc.gov/reading-rm/doc-collections/cfr/. If a request for a hearing or petition for leave to
intervene is filed by the above date, the Commission or a presiding
officer designated by the Commission or by the Chief Administrative
Judge of the Atomic Safety and Licensing Board Panel, will rule on the
request and/or petition; and the Secretary or the Chief Administrative
Judge of the Atomic Safety and Licensing Board will issue a notice of a
hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address, and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and 4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestor's/petitioner's interest. The petition must
also identify the specific contentions which the requestor/petitioner
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
requestor/petitioner shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the requestor/
petitioner intends to rely in proving the contention at the hearing.
The requestor/petitioner must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
requestor/petitioner intends to rely to establish those facts or expert
opinion. The petition must include sufficient information to show that
a genuine dispute exists with the applicant on a material issue of law
or fact. Contentions shall be limited to matters within the scope of
the amendment under consideration. The contention must be one which, if
proven, would entitle the requestor/petitioner to relief. A requestor/
petitioner who fails to satisfy these requirements with respect to at
least one contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, then any hearing
held would take place before the issuance of any amendment.
All documents filed in the 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 email 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
[[Page 38096]]
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 the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in the NRC's ``Guidance for
Electronic Submission,'' which is available on the agency's public Web
site at https://www.nrc.gov/site-help/e-submittals.html. Participants
may attempt to use other software not listed on the Web site, but
should note that the NRC's E-Filing system does not support unlisted
software, and the NRC Meta System Help Desk will not be able to offer
assistance in using unlisted software.
If a participant is electronically submitting a document to the NRC
in accordance with the E-Filing rule, the participant must file the
document using the NRC's online, Web-based submission form. In order to
serve documents through the Electronic Information Exchange System,
users will be required to install a Web browser plug-in from the NRC's
Web site. Further information on the Web-based submission form,
including the installation of the Web browser plug-in, is available on
the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals.html.
Once a participant has obtained a digital ID certificate and a
docket has been created, the participant can then submit a request for
hearing or petition for leave to intervene. Submissions should be in
Portable Document Format (PDF) in accordance with the NRC guidance
available on the NRC's public Web site at https://www.nrc.gov/site-help/e-submittals.html. A filing is considered complete at the time the
documents are submitted through the NRC's E-Filing system. To be
timely, an electronic filing must be submitted to the E-Filing system
no later than 11:59 p.m. Eastern Time on the due date. Upon receipt of
a transmission, the E-Filing system time-stamps the document and sends
the submitter an email notice confirming receipt of the document. The
E-Filing system also distributes an email notice that provides access
to the document to the NRC's 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's Web site
at https://www.nrc.gov/site-help/e-submittals.html, by email 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 the
NRC's electronic hearing docket which is available to the public at
https://ehd1.nrc.gov/ehd/, unless excluded pursuant to an order of the
Commission, or the presiding officer. Participants are requested not to
include personal privacy information, such as social security numbers,
home addresses, or home phone numbers in their filings, unless an NRC
regulation or other law requires submission of such information. With
respect to copyrighted works, except for limited excerpts that serve
the purpose of the adjudicatory filings and would constitute a Fair Use
application, participants are requested not to include copyrighted
materials in their submission.
Petitions for leave to intervene must be filed no later than 60
days from the date of publication of this notice. Non-timely filings
will not be entertained absent a determination by the presiding officer
that the petition or request should be granted or the contentions
should be admitted, based on a balancing of the factors specified in 10
CFR 2.309(c)(1)(i)-(viii).
For further details with respect to this license amendment
application, see the application for amendment which is available for
public inspection at the 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 online in the NRC Library at https://www.nrc.gov/reading-rm/adams.html. Persons who do not have access to ADAMS or who encounter
problems in accessing the documents located in ADAMS, should contact
the NRC's PDR Reference staff at 1-800-397-4209, 301-415-4737, or by
email to pdr.resource@nrc.gov.
Northern States Power Company--Minnesota, Docket No. 50-263, Monticello
Nuclear Generating Plant, Wright County, Minnesota
Date of amendment request: May 25, 2012.
Description of amendment request: The licensee proposed to revise
the licensing basis regarding the time delay assumed in the safety
analyses for the degraded voltage transfer logic associated with the
1AR Transformer, which is governed by Technical Specifications 3.3.8.1,
``Loss of Power (LOP) Instrumentation.'' Specifically, the revision
will remove the capability to automatically transfer to the 1AR
Transformer as a source of power to the essential buses on degraded
voltage and instead directly transfer to the Emergency Diesel
Generators (EDGs). This transfer will ensure that Class 1E
[[Page 38097]]
equipment is capable of performing its function to meet the
requirements of the current licensing basis.
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 (NSHC) analysis. The NRC staff reviewed the licensee's
NSHC analysis and has prepared its own as follows:
1. Does the proposed amendment involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
The proposed amendment does not affect any previously used
accident initiators or precursors, and does not change the initial
conditions contributing to the severity or consequences of
previously analyzed accidents or malfunctions. The power transfer
scheme was not a precursor of previously analyzed accidents, and
took no part in determining the consequences of previously analyzed
accidents. As a result, all previous safety analyses will continue
to meet all applicable acceptance criteria since the proposed
amendment will not degrade the performance of structures, systems,
and components (SSCs) important to safety.
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.
No new accident scenarios, precursors, failure mechanisms, or
limiting single failures will be introduced as a result of the
proposed amendment. The proposed revision of the degraded voltage
transfer logic scheme (i.e., to transfer directly to the EDG instead
of first attempting to transfer to the IAR Transformer) was
previously licensed for Monticello, and is typical for the industry.
The delay time associated with the degraded voltage transfer logic
was not postulated as an initiator of any previously analyzed
accident, and is not expected to create any new system interactions
or failure modes of any SSCs. Thus, equipment important to safety
will continue to operate as designed, and the proposed change will
not result in any adverse conditions or any increase in challenges
to safety systems.
Therefore, operation of the plant in accordance with the
proposed amendment will not create the possibility of a new or
different type 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 aims to correct non-conservative values
assumed in the analyses for the degraded voltage protection
function. The proposed amendment assures that the design
requirements of the emergency electrical power system will continue
to be met. The proposed amendment does not affect previously used
safety acceptance criteria, assumptions, scenarios, and analysis
methodology.
Therefore, the proposed amendment does not involve any reduction
in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
its own analysis, concludes that the three standards of 10 CFR 50.92(c)
are satisfied. Therefore, the NRC staff proposes to determine that the
proposed amendment involves no significant hazards consideration.
Attorney for the licensee: Peter M. Glass, Assistant General
Counsel, Xcel Energy Services, Inc., 414 Nicollet Mall, Minneapolis, MN
55401.
NRC Branch Chief: Istvan Frankl, Acting.
Union Electric Company, Docket No. 50-483, Callaway Plant, Unit 1,
Callaway County, Missouri
Date of amendment request: September 22, 2011.
Description of amendment request: The amendment would revise
Required Action B.1 of Technical Specification (TS) 3.3.6,
``Containment Purge Isolation Instrumentation,'' such that a Note would
be added to the Required Action to conditionally allow containment
mini-purge supply and exhaust valves that have been closed in
accordance with the Action to be opened under administrative controls
as required for certain operational needs. The proposed change is
similar to allowances already in place in TS 3.6.3, ``Containment
Isolation Valves,'' and TS 3.9.4, ``Containment Penetrations.''
Basis for proposed no significant hazards consideration
determination: As required by 10 CFR 50.91(a), the licensee has
provided its analysis of the issue of no significant hazards
consideration, which is presented below:
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
Overall protection system performance will remain within the
bounds of the previously performed accident analyses since there are
no design changes. All design, material, and construction standards
that were applicable prior to this amendment request will be
maintained. There will be no changes to any design or operating
limits.
The proposed change does not involve or result in any changes to
accident initiators or precursors, nor does it alter the design
assumptions or conditions of the plant. The proposed change for the
mini-purge valves which support the mitigation of certain accidents
would not affect the initiation of those accidents and therefore
does not affect the probability of occurrence of an accident.
Per the provisions of the proposed Note for Required Action B.1
of TS 3.3.6, the automatic containment isolation function(s)
associated with a Phase A containment isolation signal (which is the
trip function/signal credited in the accident analysis) would
continue to be required Operable. At the same time, the proposed
change helps to support venting of containment to ensure the initial
condition assumptions for containment pressure in the accident
analyses are met during a TS-allowed period of radiation monitor
inoperability. There are no design changes to the containment mini-
purge isolation valves or the associated actuation circuitry. There
will be no changes to the operation of these valves other than the
limited durations during which they may be open under administrative
controls with inoperable actuation instrumentation (i.e. while a TS
Required Action is in effect). Exceptions to Technical Specification
requirements are allowed in situations where plant operation would
otherwise be restricted in a manner that is not commensurate with
the desired safety objective, especially when those exceptions are
of short duration and are accompanied by compensatory measures.
Therefore, the proposed change will not alter or prevent the
capability of structures, systems, and components (SSCs) to perform
their intended functions for mitigating the consequences of an
accident as assumed in the accident analysis.
The proposed change does not physically alter the design of any
safety-related systems, nor does it affect the way in which safety-
related systems are assumed to perform their functions.
The proposed change will not affect the source term, containment
isolation, or radiological release assumptions used in evaluating
the radiological consequences of an accident previously evaluated.
The applicable radiological dose criteria will continue to be met.
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
There are no proposed design changes, nor are there any changes
in the method by which any safety-related plant structure, system,
or component (SSC) is assumed to perform its specified safety
function. The proposed change will not affect the normal method of
plant operation or change any operating parameters. Equipment
performance necessary to fulfill safety analysis missions will be
unaffected. The proposed change will not alter any assumptions
required to meet the safety analysis acceptance criteria. No new
accident scenarios, transient precursors, failure mechanisms, or
limiting single failures will be introduced as a result of this
amendment. There will be no adverse effect or challenges imposed on
any safety-related system as a result of this amendment.
[[Page 38098]]
The proposed amendment will not alter the design or performance
of the 7300 Process Protection System, Nuclear Instrumentation
System, or Solid State Protection System used in the plant
protection systems.
The proposed change does not, therefore, create the possibility
of a new or different accident from any accident previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
There will be no effect on those plant systems necessary to
assure the accomplishment of protection functions. There will be no
impact on the overpower limit, departure from nucleate boiling ratio
(DNBR) limits, heat flux hot channel factor (FQ), nuclear
enthalpy rise hot channel factor (F[Delta]H), loss of coolant
accident peak cladding temperature (LOCA PCT), peak local power
density, or any other margin of safety. Mode-specific required
shutdown margins in the COLR [Core Operating Limits Report] will not
be changed. The applicable radiological dose consequence acceptance
criteria will continue to be met. The proposed changes do not alter
the design of the containment mini-purge system or the supporting
instrumentation. As containment is a principal safety barrier to the
release of radioactivity to the environment for postulated design
basis accidents, there will be continued assurance that the
containment mini-purge isolation system will perform its intended
function of supporting containment such that the assumptions in the
accident analyses remain valid.
The proposed change does not eliminate any surveillances or
alter the frequency of surveillances required by the Technical
Specifications. None of the acceptance criteria for any accident
analysis will be changed.
Therefore, the proposed change does not involve a significant
reduction in a margin of safety.
The NRC staff has reviewed the licensee's analysis and, based on
this review, it appears that the three standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff proposes to determine that the
amendment request involves no significant hazards consideration.
Attorney for licensee: John O'Neill, Esq., Pillsbury Winthrop Shaw
Pittman LLP, 2300 N Street NW., Washington, DC 20037.
NRC Branch Chief: Michael T. Markley.
Notice of Issuance of Amendments to Facility Operating Licenses and
Combined Licenses
During the period since publication of the last biweekly notice,
the Commission has issued the following amendments. The Commission has
determined for each of these amendments that the application complies
with the standards and requirements of the Atomic Energy Act of 1954,
as amended (the Act), and the Commission's rules and regulations. The
Commission has made appropriate findings as required by the Act and the
Commission's rules and regulations in 10 CFR Chapter I, which are set
forth in the license amendment.
A notice of consideration of issuance of amendment to facility
operating license or combined license, as applicable, 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 online in the NRC Library at https://www.nrc.gov/reading-rm/adams.html. If you do not have access to ADAMS
or if there are problems in accessing the documents located in ADAMS,
contact the PDR's Reference staff at 1-800-397-4209, 301-415-4737 or by
email to pdr.resource@nrc.gov.
Carolina Power and Light Company, et al., Docket No. 50-400, Shearon
Harris Nuclear Power Plant, Unit 1, Wake and Chatham Counties, North
Carolina
Date of amendment request: August 22, 2011, as supplemented by
letter dated February 23, March 20, and April 2, 2012.
Description of amendment request: The amendment revised Technical
Specification (TS) 6.9.1.6, ``Core Operating Limits Report,'' to add
plant-specific methodology, ANP-3011 (P), ``Harris Nuclear Plant Unit 1
Realistic Large Break LOCA [loss-of-coolant accident] Analysis,''
Revision 1, that implements AREVA's NRC-approved topical report, EMF-
2103(P)(A), ``Realistic Large Break LOCA Methodology for Pressurized
Water Reactors'' Revision 0.
Date of issuance: May 30, 2012.
Effective date: As of the date of issuance and shall be implemented
within 60 days of issuance.
Amendment No.: 138.
Renewed Facility Operating License No. NPF-63: The amendment
revised the TSs and the Facility Operating License.
Date of initial notice in Federal Register: January 10, 2012 (77 FR
1516). The February 23, March 20, and April 2, 2012, supplements
provided additional information that clarified the application, did not
expand the scope of the application as originally noticed, and did not
change the NRC staff's initial proposed no significant hazards
consideration determination.
The Commission's related evaluation of the amendments is contained
in a Safety Evaluation dated May 30, 2012.
No significant hazards consideration comments received: No.
NRC Branch Chief: Douglas A. Broaddus.
Carolina Power and Light Company, et al., Docket No. 50-400, Shearon
Harris Nuclear Power Plant, Unit 1, Wake and Chatham Counties, North
Carolina
Date of application for amendment: April 28, 2011, as supplemented
by letters dated June 23,August 3, August 15, August 25, August 30,
August 31, September 6, September 7, October 20,October 21, October 28,
November 28, December 20, 2011, February 9, and March 26, 2012.
Brief description of amendment: The amendment increases the rated
thermal power (RTP)level from 2900 megawatts thermal (MWt) to 2948 MWt,
and makes technical specification changes as necessary to support
operation at the uprated power level. The change is an increase in RTP
of approximately 1.66 percent. The power uprate is characterized as a
measurement uncertainty recapture using the Cameron Leading Edge Flow
Meter CheckPlusSystem to improve plant calorimetric heat balance
measurement accuracy.
Date of issuance: May 30, 2012.
Effective date: As of the date of issuance and shall be implemented
within 120 days of issuance.
Amendment No.: 139.
Renewed Facility Operating License No. NPF-63: Amendment revises
the Technical Specifications.
Date of initial notice in Federal Register: September 13, 2011 (76
FR 56486). The June 23, August 3, August
[[Page 38099]]
15, August 25, August 30, August 31, September 6, September 7, October
20, October 21, October 28, November 28, December 20, 2011, February 9,
and March 26, 2012, supplements provided additional information that
clarified the application, did not expand the scope of the application
as originally noticed and did not change the NRC staff's initial
proposed no significant hazards consideration determination.
The Commission's related evaluation of the amendment is contained
in a safety evaluation dated May 30, 2012.
No significant hazards consideration comments received: No.
NextEra Energy Duane Arnold, LLC, Docket No. 50-331, Duane Arnold
Energy Center (DAEC), Linn County, Iowa
Date of application for amendment: May 31, 2011, as supplemented by
letters dated March 16, 2012, and April 5, 2012.
Brief description of amendment: The amendment upgrades DAEC
Emergency Action Levels based on Nuclear Energy Institute (NEI) 99-01,
Revision 5, ``Methodology for Development of Emergency Action Levels,''
using the guidance of NRC Regulatory Issue Summary 2003-18, Supplement
2, ``Use of Nuclear Energy Institute (NEI) 99-01, ``Methodology for
Development of Emergency Action Levels.''
Date of issuance: June 1, 2012.
Effective date: As of the date of issuance and shall be implemented
within 120 days.
Amendment No.: 281.
Renewed Facility Operating License No. DPR-49: The amendment
revised the Duane Arnold Energy Center Emergency Plan.
Date of initial notice in Federal Register: November 15, 2011 (76
FR 70774).
The supplemental information dated March 16, 2012, and April 5,
2012 contained clarifying information, did not change the scope of the
May 31, 2011, application on the initial no significant hazards
consideration determination, and did not expand the scope of the
original Federal Register notice.
The Commission's related evaluation of the amendment is contained
in a Safety Evaluation dated June 1, 2012.
No significant hazards consideration comments received: No.
For the Nuclear Regulatory Commission.
Dated at Rockville, Maryland, this 14th day of June 2012.
A. Louise Lund,
Deputy Director, Division of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2012-15176 Filed 6-25-12; 8:45 am]
BILLING CODE 7590-01-P