Omaha Public Power District; Notice of Withdrawal of Application for Amendment to Facility Operating License, 55632-55633 [05-18916]
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Federal Register / Vol. 70, No. 183 / Thursday, September 22, 2005 / Notices
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[FR Doc. 05–19083 Filed 9–20–05; 3:34 pm]
BILLING CODE 7555–01–P
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NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–285]
Omaha Public Power District; Notice of
Withdrawal of Application for
Amendment to Facility Operating
License
The U.S. Nuclear Regulatory
Commission (the Commission) has
granted the request of Omaha Public
Power District (the licensee) to
withdraw its July 25, 2003, application
for proposed amendment to Facility
Operating License No. DPR–40 for the
Fort Calhoun Station, Unit No. 1 (FCS),
located in Washington County,
Nebraska.
The proposed amendment would
have revised the facility technical
specifications pertaining to FCS
Technical Specification Section 3.0.2,
Table 3–2, Table 3–5, 3.6, 3.7, 3.8, and
the Definitions Section. This proposed
change would have provided a riskinformed alternative to the existing
surveillance interval for the integrated
Engineered Safety Features (ESF) and
Loss-of-Offsite Power testing required to
be performed on each ESF equipment
train during each outage. The proposed
change would have modified the
surveillance interval requirement for
these refueling interval surveillance
requirements to go to a staggered test
basis scheme. Using a staggered test
basis, only one train would be tested
each refueling outage. Omaha Public
Power District stated that this
amendment was modeled after the
Improved Standard Technical
Specifications and is based on a study
conducted by the Westinghouse Electric
Company, LLC on behalf of the
Combustion Engineering Owners Group
in topical report WCAP–15830–P,
‘‘Staggered Integrated ESF Testing,’’ and
Technical Specification Task Force 450.
The Commission had previously
issued a Notice of Consideration of
Issuance of Amendment published in
the Federal Register on August 19, 2003
(68 FR 49818). However, by letter dated
September 9, 2005, the licensee
withdrew the proposed change.
For further details with respect to this
action, see the application for
amendment dated July 25, 2003, and the
E:\FR\FM\22SEN1.SGM
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Federal Register / Vol. 70, No. 183 / Thursday, September 22, 2005 / Notices
licensee’s letter dated September 9,
2005, which withdrew the application
for the license amendment. Documents
may be examined, and/or copied for a
fee, at the NRC’s Public Document
Room (PDR), located at One White Flint
North, Public File Area 01 F21, 11555
Rockville Pike (first floor), Rockville,
Maryland. Publicly available records
will be accessible electronically from
the Agencywide Documents Access and
Management Systems (ADAMS) Public
Electronic Reading Room on the internet
at the NRC Web site, 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, or 301–415–4737 or by e-mail
to pdr@nrc.gov.
Dated at Rockville, Maryland, this 14th day
of September 2005.
For the Nuclear Regulatory Commission.
Alan B. Wang,
Project Manager, Section 2, Project
Directorate IV, Division of Licensing Project
Management, Office of Nuclear Reactor
Regulation.
[FR Doc. 05–18916 Filed 9–21–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–244]
R.E. Ginna Nuclear Power Plant, LLC,
R.E. Ginna Nuclear Power Plant; Notice
of Consideration of Issuance of
Amendment to Facility Operating
License and Opportunity for a Hearing
The U.S. Nuclear Regulatory
Commission (the Commission) is
considering issuance of an amendment
to Facility Operating License No. DPR–
18, issued to R.E. Ginna Nuclear Power
Plant, LLC (the licensee), for operation
of the R.E. Ginna Nuclear Power Plant
(Ginna) located in Wayne County, New
York.
The proposed amendment would
revise the facility operating license and
technical specifications (TSs) to
authorize an increase in the maximum
steady-state thermal power level at
Ginna from 1520 megawatts thermal
(MWt) to 1775 MWt, which is a 16.8
percent increase. This increase in power
level is generally referred to as an
extended power uprate. Specifically, the
proposed amendment would change the
TSs to revise: (1) The Definition of
Rated Thermal Power (RTP), (2) the RTP
for the Required Action for Condition O
in Limiting Condition for Operation
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14:53 Sep 21, 2005
Jkt 205001
(LCO) 3.3.1, ‘‘Reactor Trip System,’’ (3)
the Power Range Neutron Flux—High
Limiting Safety System Setting, (4) the
Reactor Trip System Interlocks—Power
Range Neutron Flux, P–8 Limiting
Safety System Setting, (5) the RTP
reference in Table 3.3.1–1, Footnote (h),
(6) the Steam Line Isolation High Steam
Flow Limiting Safety System Setting, (7)
the Steam Line Isolation High—High
Steam Flow Limiting Safety System
Setting, (8) decrease the upper lift
setting in LCO 3.4.10, ‘‘Pressurizer
Safety Valves,’’ (9) the required volume
in surveillance requirement (SR) 3.7.6.1
for TS 3.7.6, ‘‘Condensate Storage Tanks
(CSTs).’’ In addition, the proposed
amendment would change the TSs to
provide margin improvement, but are
not part of the extended power uprate
(EPU), to revise: (1) The Safety Injection
Pressurizer Pressure—Low Limiting
Safety System Setting, (2) the
Containment Spray Containment
Pressure—High High Limiting Safety
System Settings for narrow range and
wide range, and (3) the Steam Line
Isolation Coincident with Tavg-Low
Limiting Safety System Setting. The
proposed amendment also includes a
change to the licensing basis for control
room dose for the loss-of-coolant
accident and the rod ejection accident
dose consequences because of the EPU
conditions.
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.
Within 60 days after the date of
publication of this notice, the licensee
may file a request for a hearing with
respect to issuance of the amendment to
the subject facility operating license and
any person whose interest may be
affected by this proceeding and who
wishes to participate as a party in the
proceeding must file a written request
for a hearing and a petition for leave to
intervene. 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 persons should
consult a current copy of 10 CFR 2.309,
which is available at the Commission’s
public document room (PDR), located at
One White Flint North, Public File Area
01F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available
records will be accessible from the
Agencywide Documents Access and
Management System’s (ADAMS) Public
Electronic Reading Room on the Internet
at the NRC Web site, https://
www.nrc.gov/reading-rm/doc-
PO 00000
Frm 00019
Fmt 4703
Sfmt 4703
55633
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/requestor 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 petitioner/
requestor 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 petitioner/requestor shall
provide a brief explanation of the basis
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 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/requestor to relief.
A petitioner/requestor who fails to
satisfy these requirements with respect
to at least one contention will not be
permitted to participate as a party.
E:\FR\FM\22SEN1.SGM
22SEN1
]]>Agencies
[Federal Register Volume 70, Number 183 (Thursday, September 22, 2005)]
[Notices]
[Pages 55632-55633]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-18916]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-285]
Omaha Public Power District; Notice of Withdrawal of Application
for Amendment to Facility Operating License
The U.S. Nuclear Regulatory Commission (the Commission) has granted
the request of Omaha Public Power District (the licensee) to withdraw
its July 25, 2003, application for proposed amendment to Facility
Operating License No. DPR-40 for the Fort Calhoun Station, Unit No. 1
(FCS), located in Washington County, Nebraska.
The proposed amendment would have revised the facility technical
specifications pertaining to FCS Technical Specification Section 3.0.2,
Table 3-2, Table 3-5, 3.6, 3.7, 3.8, and the Definitions Section. This
proposed change would have provided a risk-informed alternative to the
existing surveillance interval for the integrated Engineered Safety
Features (ESF) and Loss-of-Offsite Power testing required to be
performed on each ESF equipment train during each outage. The proposed
change would have modified the surveillance interval requirement for
these refueling interval surveillance requirements to go to a staggered
test basis scheme. Using a staggered test basis, only one train would
be tested each refueling outage. Omaha Public Power District stated
that this amendment was modeled after the Improved Standard Technical
Specifications and is based on a study conducted by the Westinghouse
Electric Company, LLC on behalf of the Combustion Engineering Owners
Group in topical report WCAP-15830-P, ``Staggered Integrated ESF
Testing,'' and Technical Specification Task Force 450.
The Commission had previously issued a Notice of Consideration of
Issuance of Amendment published in the Federal Register on August 19,
2003 (68 FR 49818). However, by letter dated September 9, 2005, the
licensee withdrew the proposed change.
For further details with respect to this action, see the
application for amendment dated July 25, 2003, and the
[[Page 55633]]
licensee's letter dated September 9, 2005, which withdrew the
application for the license amendment. Documents may be examined, and/
or copied for a fee, at the NRC's Public Document Room (PDR), located
at One White Flint North, Public File Area 01 F21, 11555 Rockville Pike
(first floor), Rockville, Maryland. Publicly available records will be
accessible electronically from the Agencywide Documents Access and
Management Systems (ADAMS) Public Electronic Reading Room on the
internet at the NRC Web site, 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, or 301-415-4737 or by
e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland, this 14th day of September 2005.
For the Nuclear Regulatory Commission.
Alan B. Wang,
Project Manager, Section 2, Project Directorate IV, Division of
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 05-18916 Filed 9-21-05; 8:45 am]
BILLING CODE 7590-01-P
