Union Electric Company; Callaway Plant, Unit 1; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing, 73733-73737 [2011-30728]
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Federal Register / Vol. 76, No. 229 / Tuesday, November 29, 2011 / Notices
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Effective date: As of the date of
issuance and shall be implemented
within 60 days from the date of
issuance.
Amendment Nos.: 163/145.
Facility Operating License Nos. NPF–
68 and NPF–81: Amendments revised
the licenses and the technical
specifications.
Date of initial notice in Federal
Register: May 17, 2011 (76 FR 28476).
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated November 9,
2011.
No significant hazards consideration
comments received: No.
Southern Nuclear Operating
Company, Inc., Docket Nos. 50–424 and
50–425, Vogtle Electric Generating
Plant, Units 1 and 2, Burke County,
Georgia;
Date of application for amendments:
April 29, 2011
Brief description of amendments: The
amendments revised the Technical
Specifications (TSs) ‘‘RCS [reactor
coolant system] Leakage Detection
Instrumentation,’’ to define a new time
limit for restoring inoperable RCS
leakage detection instrument to operable
status and establish alternate methods of
monitoring RCS leakage when one or
more required monitors are inoperable.
This revision is consistent with the
Industry/Technical Specification Task
Force (TSTF) standard technical
specification traveler TSTF–513–A,
‘‘Revise PWR [pressurized water reactor]
Operability Requirements and Actions
for RCS Leakage [Detection]
Instrumentation.’’
Date of issuance: November 10, 2011.
Effective date: As of the date of
issuance and shall be implemented
within 60 days from the date of
issuance.
Amendment Nos.: 164/146.
Facility Operating License Nos. NPF–
68 and NPF–81: Amendments revised
the licenses and the technical
specifications.
Date of initial notice in Federal
Register: June 14, 2011 (76 FR 34768).
The Commission’s related evaluation
of the amendments is contained in a
Safety Evaluation dated November 10,
2011.
No significant hazards consideration
comments received: No.
For the Nuclear Regulatory Commission.
Dated at Rockville, Maryland, this 17th day
of November 2011.
Michele G. Evans,
Director, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. 2011–30525 Filed 11–28–11; 8:45 am]
BILLING CODE 7590–01–P
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NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–483; NRC–2011–0276]
Union Electric Company; Callaway
Plant, Unit 1; Notice of Consideration
of Issuance of Amendment to Facility
Operating License, Proposed No
Significant Hazards Consideration
Determination, and Opportunity for a
Hearing
Nuclear Regulatory
Commission.
ACTION: Notice of license amendment
request, opportunity to comment,
opportunity to request a hearing.
AGENCY:
Comments must be filed by
December 29, 2011. A request for a
hearing must be filed January 30, 2012.
ADDRESSES: Please include Docket ID
NRC–2011–0276 in the subject line of
your comments. For additional
instructions on submitting comments
and instructions on accessing
documents related to this action, see
‘‘Submitting Comments and Accessing
Information’’ in the SUPPLEMENTARY
INFORMATION section of this document.
You may submit comments by any one
of the following methods:
• Federal Rulemaking Web Site: Go to
https://www.regulations.gov and search
for documents filed under Docket ID
NRC–2011–0276. 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.
SUPPLEMENTARY INFORMATION:
DATES:
Submitting Comments and Accessing
Information
Comments submitted in writing or in
electronic form will be posted on the
NRC Web site and on the Federal
rulemaking Web site, https://
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
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comments to remove any identifying or
contact information, and therefore, they
should not include any information in
their comments that they do not want
publicly disclosed.
You can access publicly available
documents related to this document
using the following methods:
• NRC’s Public Document Room
(PDR): The public may examine and
have copied, for a fee, publicly available
documents at the NRC’s PDR, O1–F21,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): Publicly available documents
created or received at the NRC are
available online in the NRC Library at
https://www.nrc.gov/reading-rm/
adams.html. From this page, the public
can gain entry into ADAMS, which
provides text and image files of the
NRC’s public documents. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC’s
PDR reference staff at 1-(800) 397–4209,
(301) 415–4737, or by email to
pdr.resource@nrc.gov. The application
for amendment, dated December 10,
2010, as supplemented by letters dated
June 16, 2011, and October 27, 2011, are
available electronically under ADAMS
Accession Nos. ML103470204,
ML111680233 and ML113010383,
respectively.
• Federal Rulemaking Web Site:
Public comments and supporting
materials related to this notice can be
found at https://www.regulations.gov by
searching on Docket ID NRC–2011–
0276.
FOR FURTHER INFORMATION CONTACT:
Mohan C. Thadani, Senior Project
Manager, Plant Licensing Branch IV,
Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation,
U.S. Nuclear Regulatory Commission,
Washington, DC 20555. Telephone:
(301) 415–1476; fax number: (301) 415–
2102 email: mohan.thadani@nrc.gov.
The U.S. Nuclear Regulatory
Commission (NRC or the Commission)
is considering issuance of an
amendment to Facility Operating
License No. NPF–30 issued to Union
Electric Company (the licensee) for
operation of the Callaway Plant, Unit 1,
located in Callaway County, Missouri.
The license amendment request was
originally noticed in the Federal
Register on March 8, 2011 (76 FR
12766). This notice is being reissued in
its entirety to include a revised
description of the amendment request.
The proposed amendment would add a
new Surveillance Requirement (SR)
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3.3.8.6 to Technical Specification (TS)
3.3.8, ‘‘Emergency Exhaust System
(EES) Actuation Instrumentation.’’ The
new SR would require the performance
of response time testing on the portion
of the EES required to isolate the normal
fuel building ventilation exhaust flow
path and initiate the fuel building
ventilation isolation signal (FBVIS)
mode of operation. The proposed
amendment also would revise TS Table
3.3.8–1 to indicate that new SR 3.3.8.6
applies to automatic actuation Function
2, ‘‘Automatic Actuation Logic and
Actuation Relays (BOP ESFAS),’’ and
Function 3, ‘‘Fuel Building Exhaust
Radiation—Gaseous.’’ In addition, the
specified frequency of new SR 3.3.8.6
would be relocated and controlled in
accordance with the licensee’s
Surveillance Frequency Control
Program in accordance with guidance in
Nuclear Energy Institute (NEI) 04–10,
‘‘Risk-Informed Technical
Specifications Initiative 5b, RiskInformed Method for Control of
Surveillance Frequencies.’’ Finally,
there would be corresponding changes
to the Final Safety Analysis Report
(FSAR).
Before issuance of the proposed
license amendment, the Commission
will have made findings required by the
Atomic Energy Act of 1954, as amended
(the Act), and the Commission’s
regulations.
The Commission has made a
proposed determination that the
amendment request involves no
significant hazards consideration. Under
the Commission’s regulations in Title 10
of the Code of Federal Regulations (10
CFR), Section 50.92, this means that
operation of the facility 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. As required by 10 CFR
50.91(a), the licensee has provided its
analysis of the issue of no significant
hazards consideration, which the
Commission issued in the Federal
Register on March 8, 2011 (76 FR
12766). The Commission is issuing a
modified no significant hazards
consideration to consider aspects of the
SR 3.3.8.6 relocation to the Surveillance
Frequency Control Program. The NRC
previously approved the relocation of
surveillance frequencies as part of
Callaway Plant’s License Amendment
No. 202, as noted in the Federal
Register on January 11, 2011 (76 FR
1649).
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1. Does the proposed change involve a
significant increase in the probability or
consequences of an accident previously
evaluated?
Response: No.
There are no design changes associated
with the proposed change. All design,
material, and construction standards that
were applicable prior to this amendment
request will continue to be applicable.
The proposed change will not affect
accident initiators or precursors nor
adversely alter the design assumptions,
conditions, and configuration of the facility
or the manner in which the plant is operated
and maintained with respect to such
initiators or precursors. There will be no
change to fuel handling methods and
procedures.
Therefore, there will be no changes that
would serve to increase the likelihood of
occurrence of a fuel handling accident.
The proposed change changes a
performance requirement, but it does not
physically alter safety-related systems nor
affect the way in which safety-related
systems perform their functions.
The proposed TS change will serve to
assure that the fuel building ventilation
exhaust ESF [emergency safety feature]
response time is tested and confirmed to be
in accordance with the system design and
consistent with the assumptions of the fuel
building FHA [fuel handling accident]
analysis (as revised). As such, the proposed
change will not alter or prevent the capability
of structures, systems, and components
(SSCs) to perform their intended functions
for mitigating the consequences of an
accident and meeting applicable acceptance
limits.
The proposed change will not affect the
source term used in evaluating the
radiological consequences of a fuel handling
accident in the fuel building. However, the
Fuel Building Ventilation Exhaust ESF
response time has been increased to 90
seconds in recognition of the total delay
times involved in the generation of a fuel
building ventilation isolation signal (FBVIS)
and the times required for actuated
components to change state to their required
safety configurations. Consequently, the fuel
handling accident radiological consequences
as reported in FSAR [Final Safety Analysis
Report] Table 15.7–8 have increased.
However, the increases are much less than
the upper limit of ‘‘minimal’’ as defined
pursuant to 10 CFR 50.59(c)(2)(iii) and NEI
[Nuclear Energy Institute] 96–07 Revision 1
[‘‘Guidelines for 10 CFR 50.59
Implementation,’’ November 2000].
Therefore, there is no significant increase in
the calculated consequences of a postulated
design basis fuel handling accident in the
fuel building. The applicable radiological
dose criteria of 10 CFR 100.11, 10 CFR 50
Appendix A General Design Criterion 19, and
SRP [NUREG–0800, ‘‘Standard Review Plan
for the Review of Safety Analysis Reports for
Nuclear Power Plants: LWR [Light-WaterReactor] Edition’’] 15.7.4 will continue to be
met. New SR 3.3.8.6 is added to ensure
system performance consistent with the
accident analyses and associated dose
calculations (as revised).
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[The licensee’s request in its letter dated
October 27, 2011, for relocating the specified
frequency of new SR 3.3.8.6 to the licenseecontrolled Surveillance Frequency Control
Program is the type of SR whose relocation
to the licensee’s Surveillance Frequency
Control Program was previously approved in
Amendment No. 202, dated July 29, 2011
(ADAMS Accession No. ML111661877). That
amendment was approved based on the
conclusion that the change did not involve a
significant increase in the probability or
consequences of accidents previously
evaluated.]
Therefore, the proposed change does not
involve a significant increase in the
probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the
possibility of a new or different kind of
accident from any accident previously
evaluated?
Response: No.
With respect to any new or different kind
of accident, there are no proposed design
changes nor are there any changes in the
method by which any safety-related plant
SSC performs its specified safety function.
The proposed change will not affect the
normal method of plant operation or change
any operating parameters. No new accident
scenarios, transient precursors, failure
mechanisms, or limiting single failures will
be introduced as a result of this amendment.
The proposed amendment will not alter the
design or performance of the 7300 Process
Protection System, Nuclear Instrumentation
System, Solid State Protection System, BOP
ESFAS, MSFIS [Main Steam and Feed
Isolation System], or LSELS [Load Shedding
and Emergency Load Sequencing] used in the
plant protection systems.
[The licensee’s request in its letter dated
October 27, 2011, for relocating the specified
frequency of new SR 3.3.8.6 to the licenseecontrolled Surveillance Frequency Control
Program is the type of SR whose relocation
to the licensee’s Surveillance Frequency
Control Program was previously approved in
Amendment No. 202, dated July 29, 2011
(ADAMS Accession No. ML111661877). That
amendment was approved based on the
determination that the change does not
involve a possibility of creating a new or
different kind of accident].
The proposed change does not, therefore,
create the possibility of a new or different
accident from any accident previously
evaluated.
3. Does the proposed change involve a
significant reduction in a margin of safety?
Response: No.
There will be no effect on those plant
systems necessary to assure the
accomplishment of protection functions
associated with reactor operation or the
reactor coolant system. There will be no
impact on the overpower limit, departure
from nucleate boiling ratio (DNBR) limits,
heat flux hot channel factor (FQ), nuclear
enthalpy rise hot channel factor (FDH), loss
of coolant accident peak cladding
temperature (LOCA PCT), peak local power
density, or any other limit and associated
margin of safety. Required shutdown margins
in the COLR [Core Operating Limits Report]
will not be changed.
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The proposed change does not eliminate
any surveillances or alter the frequency of
surveillances required by the Technical
Specifications. The proposed change would
add a new Technical Specification
Surveillance Requirement for assuring the
satisfactory performance of the fuel building
ventilation exhaust ESF function in response
to a[n] FBVIS. The accident analysis for a
fuel handling accident in the fuel building
was re-performed to support the proposed
Fuel Building Ventilation Exhaust ESF
response time, and this reanalysis
demonstrated that the acceptance criteria
continue to be met with only a slight increase
in radiological consequences (i.e., less than
one percent).
[The licensee’s request in its letter dated
October 27, 2011, for relocating the specified
frequency of new SR 3.3.8.6 to the licenseecontrolled Surveillance Frequency Control
Program is the type of SR whose relocation
to the licensee’s Surveillance Frequency
Control Program was previously approved in
Amendment No. 202, dated July 29, 2011
(ADAMS Accession No. ML111661877). That
amendment was approved based on the
determination that the proposed change
would not result in a significant reduction of
margin of safety.]
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.
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 60day 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,
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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 Commission’s PDR,
located at One White Flint North, Public
File Area O1F21, 11555 Rockville Pike
(first floor), Rockville, Maryland. NRC
regulations are accessible electronically
from the NRC Library on the NRC Web
site at 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
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73735
statement of the alleged facts or expert
opinion which support the contention
and on which the 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
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 petitioner to relief. A
requestor/petitioner who fails to satisfy
these requirements with respect to at
least one contention will not be
permitted to participate as a party.
Those permitted to intervene become
parties to the proceeding, subject to any
limitations in the order granting leave to
intervene, and have the opportunity to
participate fully in the conduct of the
hearing.
If a hearing is requested, the
Commission will make a final
determination on the issue of no
significant hazards consideration. The
final determination will serve to decide
when the hearing is held. If the final
determination is that the amendment
request involves no significant hazards
consideration, the Commission may
issue the amendment and make it
immediately effective, notwithstanding
the request for a hearing. Any hearing
held would take place after issuance of
the amendment. If the final
determination is that the amendment
request involves a significant hazards
consideration, any hearing held would
take place before the issuance of any
amendment.
All documents filed in NRC
adjudicatory proceedings, including a
request for hearing, a petition for leave
to intervene, any motion or other
document filed in the proceeding prior
to the submission of a request for
hearing or petition to intervene, and
documents filed by interested
governmental entities participating
under 10 CFR 2.315(c), must be filed in
accordance with the NRC E-Filing rule
(72 FR 49139, August 28, 2007). The 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.
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To comply with the procedural
requirements of E-Filing, at least ten
(10) days prior to the filing deadline, the
participant should contact the Office of
the Secretary by email at
hearing.docket@nrc.gov, or by telephone
at (301) 415–1677, to request (1) a
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representative) to digitally sign
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server for any proceeding in which it is
participating; and (2) advise the
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hearing (even in instances in which the
participant, or its counsel or
representative, already holds an NRCissued digital ID certificate). Based upon
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establish an electronic docket for the
hearing in this proceeding if the
Secretary has not already established an
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Information about applying for a
digital ID certificate is available on
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www.nrc.gov/site-help/e-submittals/
apply-certificates.html. System
requirements for accessing the ESubmittal server are detailed in NRC’s
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If a participant is electronically
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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
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https://www.nrc.gov/site-help/esubmittals.html. A filing is considered
complete at the time the documents are
submitted through the NRC’s E-Filing
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system. To be timely, an electronic
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Participants who believe that they
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Commission, Washington, DC 20555–
0001, Attention: Rulemaking and
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a participant or party to use E-Filing if
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ehd1.nrc.gov/EHD/, unless excluded
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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 dated
December 10, 2010, as supplemented by
letters dated June 16, 2011, and October
27, 2011, which is available for public
inspection at the Commission’s PDR,
located at One White Flint North, File
Public Area O1 F21, 11555 Rockville
Pike (first floor), Rockville, Maryland.
Publicly available documents created or
received at the NRC are accessible
electronically through ADAMS in the
NRC Library at 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 PDR Reference staff by
telephone at 1–800–397–4209, (301)
415–4737, or by email to
pdr.resource@nrc.gov.
Attorney for licensee: John O’Neill,
Esq., Pillsbury Winthrop Shaw Pittman
LLP, 2300 N Street NW., Washington,
DC 20037.
Dated at Rockville, Maryland, this 22nd
day of November 2011.
E:\FR\FM\29NON1.SGM
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Federal Register / Vol. 76, No. 229 / Tuesday, November 29, 2011 / Notices
For the Nuclear Regulatory Commission.
Mohan C. Thadani,
Senior Project Manager, Plant Licensing
Branch IV, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
Week of December 12, 2011—Tentative
Tuesday, December 13, 2011
9 a.m. Briefing on NFPA 805 Fire
Protection (Public Meeting)(Contact:
Alex Klein, (301) 415–2822)
[FR Doc. 2011–30728 Filed 11–28–11; 8:45 am]
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
BILLING CODE 7590–01–P
Week of December 19, 2011—Tentative
NUCLEAR REGULATORY
COMMISSION
There are no meetings scheduled for
the week of December 19, 2011.
[NRC–2011–0006]
Week of December 26, 2011—Tentative
Sunshine Act Meeting
AGENCY HOLDING THE MEETINGS:
Nuclear
Regulatory Commission.
Weeks of November 28,
December 5, 12, 19, 26, 2011, January 2,
2012.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and Closed.
DATES:
Week of November 28, 2011
Tuesday, November 29, 2011
9:25 a.m. Affirmation Session (Public
Meeting) (Tentative)
a. U.S. Department of Energy (HighLevel Waste Repository), Docket No. 63–
001–HLW; Staff Petition for the
Commission to Exercise its Inherent
Supervisory Authority to Review Board
Orders Regarding Preservation of
Licensing Support Network (LSN)
Documents Collection, and Staff
Request for Stay (Tentative)
b. Final Rule: Requirements for
Fingerprint—Based Criminal History
Records Checks for Individuals Seeking
Unescorted Access to Nonpower
Reactors (Research or Test Reactors)
(RIN 3150–A125) (Tentative)
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
9:30 a.m. Meeting with the Advisory
Committee on Reactor Safeguards
(ACRS) (Public Meeting) (Contact:
Tanny Santos, (301) 415–7270)
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
mstockstill on DSK4VPTVN1PROD with NOTICES
Thursday, December 1, 2011
9:30 a.m. Briefing on Equal
Employment Opportunity (EEO) and
Small Business Programs (Public
Meeting) (Contact: Barbara Williams,
(301) 415–7388)
This meeting will be webcast live at
the Web address—https://www.nrc.gov.
Week of December 5, 2011—Tentative
There are no meetings scheduled for
the week of December 5, 2011.
VerDate Mar<15>2010
15:20 Nov 28, 2011
Jkt 226001
There are no meetings scheduled for
the week of December 26, 2011.
Week of January 2, 2012—Tentative
There are no meetings scheduled for
the week of January 2, 2012.
*
*
*
*
*
* The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings,
call (recording)—(301) 415–1292.
Contact person for more information:
Rochelle Bavol, (301) 415–1651.
*
*
*
*
*
The NRC Commission Meeting
Schedule can be found on the Internet
at: https://www.nrc.gov/public-involve/
public-meetings/schedule.html.
*
*
*
*
*
The NRC provides reasonable
accommodation to individuals with
disabilities where appropriate. If you
need a reasonable accommodation to
participate in these public meetings, or
need this meeting notice or the
transcript or other information from the
public meetings in another format (e.g.
braille, large print), please notify Bill
Dosch, Chief, Work Life and Benefits
Branch, at (301) 415–6200, TDD: (301)
415–2100, or by email at
william.dosch@nrc.gov. Determinations
on requests for reasonable
accommodation will be made on a caseby-case basis.
*
*
*
*
*
This notice is distributed
electronically to subscribers. If you no
longer wish to receive it, or would like
to be added to the distribution, please
contact the Office of the Secretary,
Washington, DC 20555 (301) 415–1969),
or send an email to
darlene.wright@nrc.gov.
Dated: November 23, 2011.
Rochelle C. Bavol,
Policy Coordinator, Office of the Secretary.
[FR Doc. 2011–30839 Filed 11–25–11; 4:15 pm]
BILLING CODE 7590–01–P
PO 00000
Frm 00156
Fmt 4703
Sfmt 4703
73737
NUCLEAR REGULATORY
COMMISSION
[NRC–2011–0277]
Notice of Opportunity for Public
Comment on the Proposed Model
Safety Evaluation for Plant-Specific
Adoption of Technical Specifications
Task Force Traveler TSTF–505,
Revision 1, ‘‘Provide Risk-Informed
Extended Completion Times—RITSTF
Initiative 4B’’
Nuclear Regulatory
Commission.
ACTION: Notice of opportunity for public
comment.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is requesting public
comment on the proposed model safety
evaluation (SE) for plant-specific
adoption of Technical Specifications
(TS) Task Force (TSTF) Traveler TSTF–
505, Revision 1, ‘‘Provide Risk-Informed
Extended Completion Times—RITSTF
Initiative 4B.’’ TSTF–505, Revision 1, is
available in the Agencywide Documents
Access and Management System
(ADAMS) under Accession Number
ML111650552; the model application is
available in ADAMS under Accession
Number ML112850506. The proposed
model SE for plant-specific adoption of
TSTF–505, Revision 1, is available
electronically under ADAMS Accession
Number ML112690239.
The proposed amendment would
modify the TS requirements related to
Completion Times (CTs) for Required
Actions to provide the option to
calculate a longer, risk-informed CT. A
new program, the Risk-Informed
Completion Time (RICT) Program, is
added to TS Section 5, Administrative
Controls. The proposed change revises
the Improved Standard Technical
Specification (ISTS), NUREGs–1430,
–1431, –1432, –1433, and –1434.
DATES: The comment period expires on
December 30, 2011. Comments received
after this date will be considered, if it
is practical to do so, but the NRC is able
to ensure consideration only for
comments received on or before this
date.
SUMMARY:
You may submit comments
by any one of the following methods.
Please include Docket ID NRC–2011–
0277 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 https://
www.regulations.gov. Because your
comments will not be edited to remove
any identifying or contact information,
the NRC cautions you against including
ADDRESSES:
E:\FR\FM\29NON1.SGM
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]]>Agencies
[Federal Register Volume 76, Number 229 (Tuesday, November 29, 2011)]
[Notices]
[Pages 73733-73737]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2011-30728]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-483; NRC-2011-0276]
Union Electric Company; Callaway Plant, Unit 1; Notice of
Consideration of Issuance of Amendment to Facility Operating License,
Proposed No Significant Hazards Consideration Determination, and
Opportunity for a Hearing
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of license amendment request, opportunity to comment,
opportunity to request a hearing.
-----------------------------------------------------------------------
DATES: Comments must be filed by December 29, 2011. A request for a
hearing must be filed January 30, 2012.
ADDRESSES: Please include Docket ID NRC-2011-0276 in the subject line
of your comments. For additional instructions on submitting comments
and instructions on accessing documents related to this action, see
``Submitting Comments and Accessing Information'' in the SUPPLEMENTARY
INFORMATION section of this document. You may submit comments by any
one of the following methods:
Federal Rulemaking Web Site: Go to https://www.regulations.gov and search for documents filed under Docket ID NRC-
2011-0276. 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.
SUPPLEMENTARY INFORMATION:
Submitting Comments and Accessing Information
Comments submitted in writing or in electronic form will be posted
on the NRC Web site and on the Federal rulemaking Web site, https://www.regulations.gov. Because your comments will not be edited to remove
any identifying or contact information, the NRC cautions you against
including any information in your submission that you do not want to be
publicly disclosed.
The NRC requests that any party soliciting or aggregating comments
received from other persons for submission to the NRC inform those
persons that the NRC will not edit their comments to remove any
identifying or contact information, and therefore, they should not
include any information in their comments that they do not want
publicly disclosed.
You can access publicly available documents related to this
document using the following methods:
NRC's Public Document Room (PDR): The public may examine
and have copied, for a fee, publicly available documents at the NRC's
PDR, O1-F21, One White Flint North, 11555 Rockville Pike, Rockville,
Maryland 20852.
NRC's Agencywide Documents Access and Management System
(ADAMS): Publicly available documents created or received at the NRC
are available online in the NRC Library at https://www.nrc.gov/reading-rm/adams.html. From this page, the public can gain entry into ADAMS,
which provides text and image files of the NRC's public documents. If
you do not have access to ADAMS or if there are problems in accessing
the documents located in ADAMS, contact the NRC's PDR reference staff
at 1-(800) 397-4209, (301) 415-4737, or by email to
pdr.resource@nrc.gov. The application for amendment, dated December 10,
2010, as supplemented by letters dated June 16, 2011, and October 27,
2011, are available electronically under ADAMS Accession Nos.
ML103470204, ML111680233 and ML113010383, respectively.
Federal Rulemaking Web Site: Public comments and
supporting materials related to this notice can be found at https://www.regulations.gov by searching on Docket ID NRC-2011-0276.
FOR FURTHER INFORMATION CONTACT: Mohan C. Thadani, Senior Project
Manager, Plant Licensing Branch IV, Division of Operating Reactor
Licensing, Office of Nuclear Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington, DC 20555. Telephone: (301) 415-1476;
fax number: (301) 415-2102 email: mohan.thadani@nrc.gov.
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is
considering issuance of an amendment to Facility Operating License No.
NPF-30 issued to Union Electric Company (the licensee) for operation of
the Callaway Plant, Unit 1, located in Callaway County, Missouri.
The license amendment request was originally noticed in the Federal
Register on March 8, 2011 (76 FR 12766). This notice is being reissued
in its entirety to include a revised description of the amendment
request. The proposed amendment would add a new Surveillance
Requirement (SR)
[[Page 73734]]
3.3.8.6 to Technical Specification (TS) 3.3.8, ``Emergency Exhaust
System (EES) Actuation Instrumentation.'' The new SR would require the
performance of response time testing on the portion of the EES required
to isolate the normal fuel building ventilation exhaust flow path and
initiate the fuel building ventilation isolation signal (FBVIS) mode of
operation. The proposed amendment also would revise TS Table 3.3.8-1 to
indicate that new SR 3.3.8.6 applies to automatic actuation Function 2,
``Automatic Actuation Logic and Actuation Relays (BOP ESFAS),'' and
Function 3, ``Fuel Building Exhaust Radiation--Gaseous.'' In addition,
the specified frequency of new SR 3.3.8.6 would be relocated and
controlled in accordance with the licensee's Surveillance Frequency
Control Program in accordance with guidance in Nuclear Energy Institute
(NEI) 04-10, ``Risk-Informed Technical Specifications Initiative 5b,
Risk-Informed Method for Control of Surveillance Frequencies.''
Finally, there would be corresponding changes to the Final Safety
Analysis Report (FSAR).
Before issuance of the proposed license amendment, the Commission
will have made findings required by the Atomic Energy Act of 1954, as
amended (the Act), and the Commission's regulations.
The Commission has made a proposed determination that the amendment
request involves no significant hazards consideration. Under the
Commission's regulations in Title 10 of the Code of Federal Regulations
(10 CFR), Section 50.92, this means that operation of the facility 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. As required
by 10 CFR 50.91(a), the licensee has provided its analysis of the issue
of no significant hazards consideration, which the Commission issued in
the Federal Register on March 8, 2011 (76 FR 12766). The Commission is
issuing a modified no significant hazards consideration to consider
aspects of the SR 3.3.8.6 relocation to the Surveillance Frequency
Control Program. The NRC previously approved the relocation of
surveillance frequencies as part of Callaway Plant's License Amendment
No. 202, as noted in the Federal Register on January 11, 2011 (76 FR
1649).
1. Does the proposed change involve a significant increase in
the probability or consequences of an accident previously evaluated?
Response: No.
There are no design changes associated with the proposed change.
All design, material, and construction standards that were
applicable prior to this amendment request will continue to be
applicable.
The proposed change will not affect accident initiators or
precursors nor adversely alter the design assumptions, conditions,
and configuration of the facility or the manner in which the plant
is operated and maintained with respect to such initiators or
precursors. There will be no change to fuel handling methods and
procedures.
Therefore, there will be no changes that would serve to increase
the likelihood of occurrence of a fuel handling accident.
The proposed change changes a performance requirement, but it
does not physically alter safety-related systems nor affect the way
in which safety-related systems perform their functions.
The proposed TS change will serve to assure that the fuel
building ventilation exhaust ESF [emergency safety feature] response
time is tested and confirmed to be in accordance with the system
design and consistent with the assumptions of the fuel building FHA
[fuel handling accident] analysis (as revised). As such, the
proposed change will not alter or prevent the capability of
structures, systems, and components (SSCs) to perform their intended
functions for mitigating the consequences of an accident and meeting
applicable acceptance limits.
The proposed change will not affect the source term used in
evaluating the radiological consequences of a fuel handling accident
in the fuel building. However, the Fuel Building Ventilation Exhaust
ESF response time has been increased to 90 seconds in recognition of
the total delay times involved in the generation of a fuel building
ventilation isolation signal (FBVIS) and the times required for
actuated components to change state to their required safety
configurations. Consequently, the fuel handling accident
radiological consequences as reported in FSAR [Final Safety Analysis
Report] Table 15.7-8 have increased. However, the increases are much
less than the upper limit of ``minimal'' as defined pursuant to 10
CFR 50.59(c)(2)(iii) and NEI [Nuclear Energy Institute] 96-07
Revision 1 [``Guidelines for 10 CFR 50.59 Implementation,'' November
2000]. Therefore, there is no significant increase in the calculated
consequences of a postulated design basis fuel handling accident in
the fuel building. The applicable radiological dose criteria of 10
CFR 100.11, 10 CFR 50 Appendix A General Design Criterion 19, and
SRP [NUREG-0800, ``Standard Review Plan for the Review of Safety
Analysis Reports for Nuclear Power Plants: LWR [Light-Water-Reactor]
Edition''] 15.7.4 will continue to be met. New SR 3.3.8.6 is added
to ensure system performance consistent with the accident analyses
and associated dose calculations (as revised).
[The licensee's request in its letter dated October 27, 2011,
for relocating the specified frequency of new SR 3.3.8.6 to the
licensee-controlled Surveillance Frequency Control Program is the
type of SR whose relocation to the licensee's Surveillance Frequency
Control Program was previously approved in Amendment No. 202, dated
July 29, 2011 (ADAMS Accession No. ML111661877). That amendment was
approved based on the conclusion that the change did not involve a
significant increase in the probability or consequences of accidents
previously evaluated.]
Therefore, the proposed change does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
2. Does the proposed change create the possibility of a new or
different kind of accident from any accident previously evaluated?
Response: No.
With respect to any new or different kind of accident, there are
no proposed design changes nor are there any changes in the method
by which any safety-related plant SSC performs its specified safety
function. The proposed change will not affect the normal method of
plant operation or change any operating parameters. No new accident
scenarios, transient precursors, failure mechanisms, or limiting
single failures will be introduced as a result of this amendment.
The proposed amendment will not alter the design or performance
of the 7300 Process Protection System, Nuclear Instrumentation
System, Solid State Protection System, BOP ESFAS, MSFIS [Main Steam
and Feed Isolation System], or LSELS [Load Shedding and Emergency
Load Sequencing] used in the plant protection systems.
[The licensee's request in its letter dated October 27, 2011,
for relocating the specified frequency of new SR 3.3.8.6 to the
licensee-controlled Surveillance Frequency Control Program is the
type of SR whose relocation to the licensee's Surveillance Frequency
Control Program was previously approved in Amendment No. 202, dated
July 29, 2011 (ADAMS Accession No. ML111661877). That amendment was
approved based on the determination that the change does not involve
a possibility of creating a new or different kind of accident].
The proposed change does not, therefore, create the possibility
of a new or different accident from any accident previously
evaluated.
3. Does the proposed change involve a significant reduction in a
margin of safety?
Response: No.
There will be no effect on those plant systems necessary to
assure the accomplishment of protection functions associated with
reactor operation or the reactor coolant system. There will be no
impact on the overpower limit, departure from nucleate boiling ratio
(DNBR) limits, heat flux hot channel factor (FQ), nuclear
enthalpy rise hot channel factor (F[Delta]H), loss of coolant
accident peak cladding temperature (LOCA PCT), peak local power
density, or any other limit and associated margin of safety.
Required shutdown margins in the COLR [Core Operating Limits Report]
will not be changed.
[[Page 73735]]
The proposed change does not eliminate any surveillances or
alter the frequency of surveillances required by the Technical
Specifications. The proposed change would add a new Technical
Specification Surveillance Requirement for assuring the satisfactory
performance of the fuel building ventilation exhaust ESF function in
response to a[n] FBVIS. The accident analysis for a fuel handling
accident in the fuel building was re-performed to support the
proposed Fuel Building Ventilation Exhaust ESF response time, and
this reanalysis demonstrated that the acceptance criteria continue
to be met with only a slight increase in radiological consequences
(i.e., less than one percent).
[The licensee's request in its letter dated October 27, 2011,
for relocating the specified frequency of new SR 3.3.8.6 to the
licensee-controlled Surveillance Frequency Control Program is the
type of SR whose relocation to the licensee's Surveillance Frequency
Control Program was previously approved in Amendment No. 202, dated
July 29, 2011 (ADAMS Accession No. ML111661877). That amendment was
approved based on the determination that the proposed change would
not result in a significant reduction of margin of safety.]
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.
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 Commission's PDR, located at One White Flint North, Public File
Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
NRC regulations are accessible electronically from the NRC Library on
the NRC Web site at 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 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
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 petitioner to relief. A requestor/petitioner
who fails to satisfy these requirements with respect to at least one
contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, any hearing held
would take place before the issuance of any amendment.
All documents filed in NRC adjudicatory proceedings, including a
request for hearing, a petition for leave to intervene, any motion or
other document filed in the proceeding prior to the submission of a
request for hearing or petition to intervene, and documents filed by
interested governmental entities participating under 10 CFR 2.315(c),
must be filed in accordance with the NRC E-Filing rule (72 FR 49139,
August 28, 2007). The E-Filing process requires participants to submit
and serve all adjudicatory documents over the Internet, or in some
cases to mail copies on electronic storage media. Participants may not
submit paper copies of their filings unless they seek an exemption in
accordance with the procedures described below.
[[Page 73736]]
To comply with the procedural requirements of E-Filing, at least
ten (10) days prior to the filing deadline, the participant should
contact the Office of the Secretary by email at hearing.docket@nrc.gov,
or by telephone at (301) 415-1677, to request (1) a digital ID
certificate, which allows the participant (or its counsel or
representative) to digitally sign documents and access the E-Submittal
server for any proceeding in which it is participating; and (2) advise
the Secretary that the participant will be submitting a request or
petition for hearing (even in instances in which the participant, or
its counsel or representative, already holds an NRC-issued digital ID
certificate). Based upon this information, the Secretary will establish
an electronic docket for the hearing in this proceeding if the
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 https://www.nrc.gov/site-help/e-submittals/apply-certificates.html. System requirements for accessing
the E-Submittal server are detailed in NRC's ``Guidance for Electronic
Submission,'' which is available on the agency's public Web site at
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 EIE, users will be required to install a Web
browser plug-in from the NRC Web site. Further information on the Web-
based submission form, including the installation of the Web browser
plug-in, is available on the NRC's public Web site at 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 NRC guidance
available on the NRC 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 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 https://www.nrc.gov/site-help/e-submittals.html, by email at
MSHD.Resource@nrc.gov, or by a toll-free call at (866) 672-7640. The
NRC Meta System Help Desk is available between 8 a.m. and 8 p.m.,
Eastern Time, Monday through Friday, excluding government holidays.
Participants who believe that they have a good cause for not
submitting documents electronically must file an exemption request, in
accordance with 10 CFR 2.302(g), with their initial paper filing
requesting authorization to continue to submit documents in paper
format. Such filings must be submitted by: (1) First class mail
addressed to the Office of the Secretary of the Commission, U.S.
Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention:
Rulemaking and Adjudications Staff; or (2) courier, express mail, or
expedited delivery service to the Office of the Secretary, Sixteenth
Floor, One White Flint North, 11555 Rockville Pike, Rockville,
Maryland, 20852, Attention: Rulemaking and Adjudications Staff.
Participants filing a document in this manner are responsible for
serving the document on all other participants. Filing is considered
complete by first-class mail as of the time of deposit in the mail, or
by courier, express mail, or expedited delivery service upon depositing
the document with the provider of the service. A presiding officer,
having granted an exemption request from using E-Filing, may require a
participant or party to use E-Filing if the presiding officer
subsequently determines that the reason for granting the exemption from
use of E-Filing no longer exists.
Documents submitted in adjudicatory proceedings will appear in
NRC's electronic hearing docket which is available to the public at
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 dated December 10, 2010,
as supplemented by letters dated June 16, 2011, and October 27, 2011,
which is available for public inspection at the Commission's PDR,
located at One White Flint North, File Public Area O1 F21, 11555
Rockville Pike (first floor), Rockville, Maryland. Publicly available
documents created or received at the NRC are accessible electronically
through ADAMS in the NRC Library at 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 PDR Reference staff by telephone at 1-800-397-4209, (301) 415-
4737, or by email to pdr.resource@nrc.gov.
Attorney for licensee: John O'Neill, Esq., Pillsbury Winthrop Shaw
Pittman LLP, 2300 N Street NW., Washington, DC 20037.
Dated at Rockville, Maryland, this 22nd day of November 2011.
[[Page 73737]]
For the Nuclear Regulatory Commission.
Mohan C. Thadani,
Senior Project Manager, Plant Licensing Branch IV, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2011-30728 Filed 11-28-11; 8:45 am]
BILLING CODE 7590-01-P
