Entergy Operations, Inc.; Notice of Receipt and Availability of Application for a Combined License, 14849-14850 [E8-5522]
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Federal Register / Vol. 73, No. 54 / Wednesday, March 19, 2008 / Notices
Pike, Room O–1 F21, Rockville, MD
20852. OMB clearance requests are
available at the NRC worldwide Web
site: https://www.nrc.gov/public-involve/
doc-comment/omb/. The
document will be available on the NRC
home page site for 60 days after the
signature date of this notice.
Comments and questions about the
information collection requirements
may be directed to the NRC Clearance
Officer, Margaret A. Janney (T–5 F52),
U.S. Nuclear Regulatory Commission,
Washington, DC 20555–0001, by
telephone at 301–415–7245, or by e-mail
to INFOCOLLECTS@NRC.GOV.
Dated at Rockville, Maryland, this 12th day
of March 2008.
For the Nuclear Regulatory Commission.
Gregory Trussell,
Acting NRC Clearance Officer, Office of
Information Services.
[FR Doc. E8–5517 Filed 3–18–08; 8:45 am]
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Agency Information Collection
Activities: Proposed Collection;
Comment Request
U.S. Nuclear Regulatory
Commission (NRC).
ACTION: Notice of the OMB review of
information collection and solicitation
of public comment.
jlentini on PROD1PC65 with NOTICES
AGENCY:
SUMMARY: The NRC has recently
submitted to OMB for review the
following proposal for the collection of
information under the provisions of the
Paperwork Reduction Act of 1995 (44
U.S.C. Chapter 35). The NRC hereby
informs potential respondents that an
agency may not conduct or sponsor, and
that a person is not required to respond
to, a collection of information unless it
displays a currently valid OMB control
number. The NRC published a Federal
Register Notice with a 60-day comment
period on this information collection on
January 2, 2008.
1. Type of submission, new, revision,
or extension: Revision.
2. The title of the information
collection: 10 CFR Part 73—‘‘Physical
Protection of Plants and Materials.’’
3. Current OMB approval number:
3150–0002.
4. The form number if applicable: Not
applicable.
5. How often the collection is
required: On occasion, with the
exception of the initial submittal of
revised Security Plans, Safeguards
Contingency Plans, and Security
Training and Qualification Plans.
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Required reports are submitted and
evaluated as events occur.
6. Who will be required or asked to
report: Nuclear power reactor licensees,
licensed under 10 CFR Part 50 or 52
who possess, use, import, export,
transport, or deliver to a carrier for
transport, special nuclear material;
Category I fuel facilities; Category II and
III facilities; research and test reactors;
and 262 other nuclear materials
licensees.
7. An estimate of the number of
annual responses: 86,264 (85,880 plus
384 recordkeepers).
8. The estimated number of annual
respondents: 384.
9. An estimate of the total number of
hours needed annually to complete the
requirement or request: 578,863 hours
(85,441 reporting [approximately 1 hour
per response] and 493,422
recordkeeping [1,285 hours per
recordkeeper]).
10. Abstract: NRC regulations in 10
CFR Part 73 prescribe requirements to
establish and maintain a physical
protection system and security
organization with capabilities for
protection of: (1) Special nuclear
material (SNM) at fixed sites, (2) SNM
in transit, and (3) plants in which SNM
is used. The objective is to ensure that
activities involving special nuclear
material are consistent with interests of
common defense and security and that
these activities do not constitute an
unreasonable risk to public health and
safety. The information in the reports
and records submitted by licensees is
used by the NRC staff to ensure that the
health and safety of the public and the
environment are protected, and licensee
possession and use of special nuclear
material is in compliance with license
and regulatory requirements.
A copy of the final supporting
statement may be viewed free of charge
at the NRC Public Document Room, One
White Flint North, 11555 Rockville
Pike, Room O–1 F21, Rockville, MD
20852. OMB clearance requests are
available at the NRC worldwide Web
site: https://www.nrc.gov/public-involve/
doc-comment/omb/. The
document will be available on the NRC
home page site for 60 days after the
signature date of this notice.
Comments and questions should be
directed to the OMB reviewer listed
below by April 18, 2008. Comments
received after this date will be
considered if it is practical to do so, but
assurance of consideration cannot be
given to comments received after this
date.
Nathan J. Frey, Office of Information
and Regulatory Affairs (3150–0002),
NEOB–10202, Office of Management
PO 00000
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14849
and Budget, Washington, DC 20503.
Comments can also be e-mailed to
Nathan_J._Frey@omb.eop.gov or
submitted by telephone at (202) 395–
7345.
The NRC Clearance Officer is
Margaret A. Janney, (301) 415–7245.
Dated at Rockville, Maryland, this 12th day
of March, 2008.
For the Nuclear Regulatory Commission.
Gregory Trussell,
Acting NRC Clearance Officer, Office of
Information Services.
[FR Doc. E8–5518 Filed 3–18–08; 8:45 am]
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Entergy Operations, Inc.; Notice of
Receipt and Availability of Application
for a Combined License
On February 27, 2008, Entergy
Operations, Inc. (EOI), on behalf of itself
and Entergy Mississippi, Inc., Entergy
Louisiana, LLC, Entergy Gulf States
Louisiana, LLC, and System Energy
Resources, Inc., filed with the U. S.
Nuclear Regulatory Commission (NRC,
the Commission) pursuant to Section
103 of the Atomic Energy Act and Title
10 of the Code of Federal Regulations
(10 CFR) Part 52, ‘‘Licenses,
Certifications, and Approvals for
Nuclear Power Plants,’’ an application
for a combined license (COL) for an
economic simplified boiling water
reactor (ESBWR) nuclear power plant at
the Grand Gulf Nuclear Station (GGNS)
site located in Claiborne County,
Mississippi. The reactor is to be
identified as GGNS Unit 3.
An applicant may seek a COL in
accordance with Subpart C of 10 CFR
Part 52. The information submitted by
the applicant includes certain
administrative information such as
financial qualifications submitted
pursuant to 10 CFR 52.77, as well as
technical information submitted
pursuant to 10 CFR 52.79.
Subsequent Federal Register notices
will address the acceptability of the
tendered COL application for docketing
and provisions for participation of the
public in the COL review process.
A copy of the application is available
for public inspection at the
Commission’s Public Document Room
(PDR), located at One White Flint North,
Public File Area O1 F21, 11555
Rockville Pike (first floor), Rockville,
Maryland, and via the Agencywide
Documents Access and Management
System (ADAMS) Public Electronic
Reading Room on the Internet at the
NRC Web site, https://www.nrc.gov/
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Federal Register / Vol. 73, No. 54 / Wednesday, March 19, 2008 / Notices
reading-rm/adams.html. The accession
number for the application is
ML080640433. Future publicly available
documents related to the application
will also be posted in ADAMS. Persons
who do not have access to ADAMS, or
who encounter problems in accessing
the documents located in ADAMS,
should contact the NRC Public
Document Room staff by telephone at 1–
800–397–4209 or 301–415–4737, or by
e-mail to pdr@nrc.gov. The application
is also available at https://www.nrc.gov/
reactors/new-licensing/col.html.
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 is
presented below:
Dated at Rockville, Maryland, this 10th day
of March, 2008.
For the Nuclear Regulatory Commission.
Eric R. Oesterle,
Senior Project Manager, ESBWR/ABWR
Projects Branch 1, Division of New Reactor
Licensing, Office of New Reactors.
[FR Doc. E8–5522 Filed 3–18–08; 8:45 am]
1. Does the proposed amendment involve
a significant increase in the probability or
consequences of an accident previously
evaluated?
The probability or consequences of
accidents previously evaluated in the
[Updated Final Safety Analysis Report] are
unaffected by this proposed change. The
duration for obtaining neutron detector
plateau curves is not an initiator of any
accident previously analyzed. There is no
change to any equipment response or
accident scenario, and this change results in
no additional challenges to fission product
barrier integrity. The proposed change does
not alter the design, configuration, operation,
or function of any plant system, structure, or
component.
The requested amendment modifies the
frequency of the channel calibrations for the
intermediate and power range detectors by
permitting 24 hours to perform the SR
[surveillance requirement] (measure and
obtain neutron detector plateau curves) after
achieving steady-state operation at rated
thermal power. This change has no impact on
the consequences or probability of any
accident previously evaluated. The proposed
change does not impact the ability of the
nuclear instrumentation, reactor protection
system, or any other system, structure, or
component to perform its intended function
to mitigate the consequences of an accident
within acceptable limits. The proposed
change does not affect the source term,
containment isolation, or radiological
assumptions used in analyzing the
consequences of accidents previously
evaluated. Further, the proposed change
neither increases the type or amount of
radioactivity released offsite nor increases
public or occupational radiation exposures.
Therefore, the proposed change does not
involve a significant increase in the
probability or consequences of an accident
previously evaluated.
2. Does the proposed amendment create
the possibility of a new or different kind of
accident from any accident previously
evaluated?
No new accident scenarios, failure
mechanisms, or limiting single failures are
introduced as a result of the proposed
change. The proposed change does not
challenge the performance or integrity of any
safety-related system. The proposed change
neither installs nor removes any plant
equipment, and it does not alter the design,
physical configuration, or operation of any
plant structure, system, or component. No
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[Docket No. 50–443]
jlentini on PROD1PC65 with NOTICES
Seabrook Station, Unit No. 1; Notice of
Consideration of Issuance of
Amendment to Facility Operating
License, Proposed No Significant
Hazards; Consideration Determination
and Opportunity for a Hearing
The U.S. Nuclear Regulatory
Commission (the Commission or NRC)
is considering issuance of an
amendment to Facility Operating
License No. NPF–86 issued to FPL
Energy Seabrook, LLC (the licensee) for
operation of Seabrook Station, Unit No.
1, located in Rockingham County, New
Hampshire.
The proposed amendment would
revise Technical Specification (TS)
Table 4.3–1, ‘‘Reactor Trip System
Instrumentation Surveillance
Requirements’’ to require the initial
plateau curves to be measured within 24
hours after attaining 100 percent steadystate power. Currently, initial plateau
curves are required to be taken within
24 hours of entry into Mode 2.
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
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physical changes are being made to the plant,
so no new accident causal mechanisms are
being introduced. Therefore, the proposed
change does not create the possibility of a
new or different kind of accident from any
previously evaluated.
3. Does the proposed amendment involve
a significant reduction in a margin of safety?
The margin of safety associated with the
acceptance criteria of any accident is
unchanged. The proposed change will have
no affect on the operability or performance of
the safety-related systems and components.
The proposed change does not alter the
design, configuration, operation, or function
of any plant system, structure, or component.
The ability of any operable structure, system,
or component to perform its designated
safety function is unaffected by this change.
With this change, the TS will continue to
require operable nuclear instrumentation.
The proposed change does not create an
initiating event, increase the likelihood of an
initiating event, affect the ability to mitigate
an event, affect containment performance, or
affect operator actions in response to an
event. Therefore, the margin of safety as
defined in the TS is not reduced and 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,
any hearing will take place after
issuance. The Commission expects that
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Agencies
[Federal Register Volume 73, Number 54 (Wednesday, March 19, 2008)]
[Notices]
[Pages 14849-14850]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-5522]
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NUCLEAR REGULATORY COMMISSION
Entergy Operations, Inc.; Notice of Receipt and Availability of
Application for a Combined License
On February 27, 2008, Entergy Operations, Inc. (EOI), on behalf of
itself and Entergy Mississippi, Inc., Entergy Louisiana, LLC, Entergy
Gulf States Louisiana, LLC, and System Energy Resources, Inc., filed
with the U. S. Nuclear Regulatory Commission (NRC, the Commission)
pursuant to Section 103 of the Atomic Energy Act and Title 10 of the
Code of Federal Regulations (10 CFR) Part 52, ``Licenses,
Certifications, and Approvals for Nuclear Power Plants,'' an
application for a combined license (COL) for an economic simplified
boiling water reactor (ESBWR) nuclear power plant at the Grand Gulf
Nuclear Station (GGNS) site located in Claiborne County, Mississippi.
The reactor is to be identified as GGNS Unit 3.
An applicant may seek a COL in accordance with Subpart C of 10 CFR
Part 52. The information submitted by the applicant includes certain
administrative information such as financial qualifications submitted
pursuant to 10 CFR 52.77, as well as technical information submitted
pursuant to 10 CFR 52.79.
Subsequent Federal Register notices will address the acceptability
of the tendered COL application for docketing and provisions for
participation of the public in the COL review process.
A copy of the application is available for public inspection at the
Commission's Public Document Room (PDR), located at One White Flint
North, Public File Area O1 F21, 11555 Rockville Pike (first floor),
Rockville, Maryland, and via the Agencywide Documents Access and
Management System (ADAMS) Public Electronic Reading Room on the
Internet at the NRC Web site, https://www.nrc.gov/
[[Page 14850]]
reading-rm/adams.html. The accession number for the application is
ML080640433. Future publicly available documents related to the
application will also be posted in ADAMS. Persons who do not have
access to ADAMS, or who encounter problems in accessing the documents
located in ADAMS, should contact the NRC Public Document Room staff by
telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to
pdr@nrc.gov. The application is also available at https://www.nrc.gov/
reactors/new-licensing/col.html.
Dated at Rockville, Maryland, this 10th day of March, 2008.
For the Nuclear Regulatory Commission.
Eric R. Oesterle,
Senior Project Manager, ESBWR/ABWR Projects Branch 1, Division of New
Reactor Licensing, Office of New Reactors.
[FR Doc. E8-5522 Filed 3-18-08; 8:45 am]
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