FirstEnergy Nuclear Operating Company; Notice of Withdrawal of Application for Amendment to Facility Operating License, 16877 [E5-1451]
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Dated at Rockville, Maryland, this 28th day
of March 2005.
For the Nuclear Regulatory Commission.
Brenda Jo. Shelton,
NRC Clearance Officer, Office of Information
Services.
[FR Doc. E5–1448 Filed 3–31–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–346]
FirstEnergy Nuclear Operating
Company; Notice of Withdrawal of
Application for Amendment to Facility
Operating License
The U.S. Nuclear Regulatory
Commission (the Commission) has
granted the request of FirstEnergy
Nuclear Operating Company (the
licensee) to withdraw its October 12,
2001, application for a proposed
amendment to Facility Operating
License No. NPF–3 for the Davis-Besse
Nuclear Station, Unit 1, located in
Ottawa County, Ohio.
The proposed amendment would
have made necessary revisions to the
DBNPS technical specifications to
reflect an increase in the authorized
rated thermal power from 2772 MWt to
2817 MWt (approximately 1.63 percent),
based on the use of Caldon Inc. Leading
Edge Flow Meter (LEFM) CheckPlusTM
System instrumentation to improve the
accuracy of the feedwater mass flow
input to the plant power calorimetric
measurement.
The Commission had previously
issued a Notice of Consideration of
Issuance of Amendment published in
the Federal Register December 26, 2001
(66 FR 66467). However, by letter dated
December 20, 2004, the licensee
withdrew the proposed change.
VerDate jul<14>2003
17:15 Mar 31, 2005
Jkt 205001
For further details with respect to this
action, see the application for
amendment dated October 12, 2001, and
the licensee’s letter dated December 20,
2004, which withdrew the application
for 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 O1 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 25th day
of March 2005.
For the Nuclear Regulatory Commission.
Jon B. Hopkins,
Project Manager, Section 2, Project
Directorate III, Division of Licensing Project
Management, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–1451 Filed 3–31–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–424 and 50–425]
Southern Nuclear Operating Company,
Inc., Vogtle Electric Generating Plant,
Units 1 and 2; Exemption
1.0 Background
Southern Nuclear Operating
Company, Inc. (SNC, or the licensee) is
the holder of Facility Operating License
Nos. NPF–68 and NPF–81 that authorize
operation of the Vogtle Electric
Generating Plant, Units 1 and 2 (Vogtle,
Units 1 and 2). The license provides,
among other things, that the facility is
subject to all rules, regulations, and
orders of the Nuclear Regulatory
Commission (NRC, the Commission)
now or hereafter in effect.
The facility consists of two
pressurized water reactors located in
Burke County, Georgia.
2.0 Request/Action
Title 10 of the Code of Federal
Regulations (10 CFR) part 50, Appendix
G requires that pressure-temperature (PT) limits be established for reactor
pressure vessels (RPVs) during normal
PO 00000
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Fmt 4703
Sfmt 4703
16877
operating and hydrostatic or leak rate
testing conditions. Specifically, 10 CFR
part 50, Appendix G states that ‘‘[t]he
minimum temperature requirements
* * * pertain to the controlling
material, which is either the material in
the closure flange or the material in the
beltline region with the highest
reference temperature. * * * the
minimum temperature requirements
and the controlling material depend on
the operating condition (i.e., hydrostatic
pressure and leak tests, or normal
operation including anticipated normal
operational occurrences), the vessel
pressure, whether fuel is in the vessel,
and whether the core is critical. The
metal temperature of the controlling
material, in the region of the controlling
material which has the least favorable
combination of stress and temperature,
must exceed the appropriate minimum
temperature requirement for the
condition and pressure of the vessel
specified in Table 1 [of 10 CFR part 50,
Appendix G].’’ Footnote 2 to Table 1 in
10 CFR Part 50, Appendix G specifies
that RPV minimum temperature
requirements related to RPV closure
flange considerations shall be based on
‘‘[t]he highest reference temperature of
the material in the closure flange region
that is highly stressed by bolt preload.’’
In order to address provisions of
amendments to modify the Vogtle, Units
1 and 2 Technical Specifications to
revise the pressure-temperature limits
report methodology for each unit, SNC
requested in its submittal dated
February 26, 2004, that the staff exempt
Vogtle, Units 1 and 2 from the
application of specific requirements of
10 CFR part 50, Appendix G, as they
pertain to the establishment of
minimum temperature requirements, for
all modes of operation addressed by 10
CFR part 50, Appendix G, based on the
material properties of the material of the
RPV closure flange region that is highly
stressed by the bolt preload. The
licensee’s technical basis for this
exemption request is contained in
Enclosure 4 of its February 26, 2004,
submittal: WCAP–16142–P, Revision 1,
‘‘Reactor Vessel Closure Head/Vessel
Flange Requirements Evaluation for
Vogtle Units 1 and 2,’’ and a response
to an NRC staff request for additional
information contained in an SNC letter
dated October 22, 2004. The
requirements from which SNC
requested that Vogtle, Units 1 and 2 be
exempted shall be referred to, for the
purpose of this exemption, as those
requirements related to the application
of footnote (2) to Table 1 of 10 CFR part
50, Appendix G.
WCAP–16142–P, Revision 1 included
a fracture mechanics analysis of
E:\FR\FM\01APN1.SGM
01APN1
Agencies
[Federal Register Volume 70, Number 62 (Friday, April 1, 2005)]
[Notices]
[Page 16877]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-1451]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-346]
FirstEnergy Nuclear Operating Company; Notice of Withdrawal of
Application for Amendment to Facility Operating License
The U.S. Nuclear Regulatory Commission (the Commission) has granted
the request of FirstEnergy Nuclear Operating Company (the licensee) to
withdraw its October 12, 2001, application for a proposed amendment to
Facility Operating License No. NPF-3 for the Davis-Besse Nuclear
Station, Unit 1, located in Ottawa County, Ohio.
The proposed amendment would have made necessary revisions to the
DBNPS technical specifications to reflect an increase in the authorized
rated thermal power from 2772 MWt to 2817 MWt (approximately 1.63
percent), based on the use of Caldon Inc. Leading Edge Flow Meter
(LEFM) CheckPlusTM System instrumentation to improve the
accuracy of the feedwater mass flow input to the plant power
calorimetric measurement.
The Commission had previously issued a Notice of Consideration of
Issuance of Amendment published in the Federal Register December 26,
2001 (66 FR 66467). However, by letter dated December 20, 2004, the
licensee withdrew the proposed change.
For further details with respect to this action, see the
application for amendment dated October 12, 2001, and the licensee's
letter dated December 20, 2004, which withdrew the application for
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 O1 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 25th day of March 2005.
For the Nuclear Regulatory Commission.
Jon B. Hopkins,
Project Manager, Section 2, Project Directorate III, Division of
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. E5-1451 Filed 3-31-05; 8:45 am]
BILLING CODE 7590-01-P