Southern Nuclear Operating Company, Inc (SNC), Joseph M. Farley Nuclear Power Plant, Units 1 and 2; Notice of Availability of the Final Supplement 18 to the Generic Environmental Impact Statement for the License Renewal of Joseph M. Farley Nuclear Power Plant, Units 1 and 2, 13215 [05-5365]
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Federal Register / Vol. 70, No. 52 / Friday, March 18, 2005 / Notices
For the Nuclear Regulatory Commission.
Brenda Jo. Shelton,
NRC Clearance Officer, Office of Information
Services.
[FR Doc. 05–5368 Filed 3–17–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–348 and 50–364]
Southern Nuclear Operating Company,
Inc (SNC), Joseph M. Farley Nuclear
Power Plant, Units 1 and 2; Notice of
Availability of the Final Supplement 18
to the Generic Environmental Impact
Statement for the License Renewal of
Joseph M. Farley Nuclear Power Plant,
Units 1 and 2
Notice is hereby given that the U.S.
Nuclear Regulatory Commission (the
Commission) has published a final
plant-specific supplement to the
Generic Environmental Impact
Statement (GEIS), NUREG–1437,
regarding the renewal of operating
licenses NPF–2 and NPF–8 for an
additional 20 years of operation at
Joseph M. Farley Nuclear Power Plant
(FNP). FNP is located in Houston
County, Alabama, approximately 16.5
miles east of the City of Dothan,
Alabama. Possible alternatives to the
proposed action (license renewal)
include no action and reasonable
alternative energy sources.
Section 9.3 of the final supplement 18
states:
Based on: (1) The analysis and findings in
the GEIS (NRC 1996; 1999), (2) the
environmental report submitted by SNC
(SNC 2003), (3) consultation with Federal,
State, Tribal, and local agencies, (4) the staff’s
own independent review, and (5) the staff’s
consideration of public comments, the
recommendation of the staff is that the
Commission determine that the adverse
environmental impacts of license renewal for
Farley Units 1 and 2, are not so great that
preserving the option of license renewal for
energy planning decision makers would be
unreasonable.
The final Supplement 18 to the GEIS
is available for public inspection in the
NRC Public Document Room (PDR)
located at One White Flint North, 11555
Rockville Pike, Rockville, Maryland,
20852, between 7:30 a.m. and 4:15 p.m.
or from the Publicly Available Records
(PARS) component of NRC’s
Agencywide Documents Access and
Management System (ADAMS). ADAMS
is accessible from the NRC’s Web site at
https://www.nrc.gov/reading-rm/
adams.html (the Public Electronic
Reading Room). Persons who do not
have access to ADAMS, or who
VerDate jul<14>2003
16:14 Mar 17, 2005
Jkt 205001
encounter problems in accessing the
documents located in ADAMS, should
contact the PDR reference staff at 1–
800–397–4209, 301–415–4737, or by email to pdr@nrc.gov. In addition, the
Houston Love Memorial Library, 212
West Burdeshaw Street, Dothan,
Alabama, and the Lucy Maddox
Memorial Library, 11880 Columbia
Street, Blakely, Georgia, have agreed to
make the final plant-specific
supplement to the GEIS available for
public inspection.
FOR FURTHER INFORMATION CONTACT: Mr.
Jack Cushing, License Renewal and
Environmental Impacts Program,
Division of Regulatory Improvement
Programs, U.S. Nuclear Regulatory
Commission, Washington, DC 20555.
Mr. Cushing may be contacted at 301–
415–1424 or via e-mail at JXC9@nrc.gov.
Dated in Rockville, Maryland, this 9th day
of March, 2005.
For the Nuclear Regulatory Commission.
Pao-Tsin Kuo,
Program Director, License Renewal and
Environmental Impacts Program, Division of
Regulatory Improvement Programs, Office of
Nuclear Reactor Regulation.
[FR Doc. 05–5365 Filed 3–17–05; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–424 and 50–425]
Southern Nuclear Operating Company,
Vogtle Electric Generating Plant, Units
1 and 2; Environmental Assessment
and Finding of No Significant Impact
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an exemption from Title 10
of the Code of Federal Regulations (10
CFR) part 50, Appendix G, for Renewed
Facility Operating License Nos. NPF–68
and NPF–81, issued to Southern
Nuclear Operating Company (the
licensee), for operation of the Vogtle
Electric Generating Plant (Vogtle), Units
1, and 2, located in Waynesboro,
Georgia. Therefore, as required by 10
CFR 51.21, the NRC is issuing this
environmental assessment and finding
of no significant impact.
Environmental Assessment
Identification of the Proposed Action:
The proposed action would exempt the
licensee from the requirements of 10
CFR part 50, Appendix G, footnote 2 to
table 1, and allow the licensee to use the
methodology in Westinghouse
Commercial Atomic Power Report
(WCAP), WCAP–16142, Revision 1,
‘‘Reactor Vessel Closure Head/Vessel
PO 00000
Frm 00057
Fmt 4703
Sfmt 4703
13215
Flange Requirements Evaluation for
Vogtle Units 1 and 2,’’ to justify
eliminating the reactor vessel/head
flange region when determining
pressure-temperature (P–T) limits for
the reactor vessel.
The proposed action is in accordance
with the licensee’s application dated
February 26, 2004, as supplemented on
July 8, and October 22, 2004.
The Need for the Proposed Action:
Appendix G of 10 CFR part 50, contains
requirements for P–T limits for the
primary system, and requirements for
metal temperature of the closure head
flange and vessel flange regions. The
P–T limits are to be determined using
the methodology of American Society of
Mechanical Engineers Boiler and
Pressure Vessel Code (ASME Code),
Section XI, Appendix G, but the flange
temperature requirements are specified
in 10 CFR part 50, Appendix G. This
rule states that the metal temperature at
the closure flange regions must exceed
the material unirradiated RTNDT by at
least 120 °F for normal operation when
the pressure exceeds 20 percent of the
pre-service hydrostatic test pressure.
This requirement was originally based
on concerns about the fracture margin in
the closure flange region. During the
boltup process, outside surface stresses
in this region typically reach over 70
percent of the steady state stress,
without being at steady state
temperature. The margin of 120 °F and
the pressure limitation of 20 percent of
hydrostatic pressure were developed in
the mid-1970s using the Kla fracture
toughness to ensure that appropriate
margins would be maintained.
Improved knowledge of fracture
toughness and other issues that affect
the integrity of the reactor vessel have
led to the recent change to allow the use
of Klc in the development of P–T curves,
as contained in ASME Code Case N–
640, ‘‘Alternative Reference Fracture
Toughness for Development of P–T
Limit Curves for Section XI, Division 1.’’
ASME Code Case, N–640 has been
approved for use without conditions by
the NRC staff in Regulatory Guide 1.147,
‘‘Inservice Inspection Code Case
Acceptability, ASME Section XI,
Division 1,’’ published in June 2003.
However, P–T limit curves can still
produce operational constraints by
limiting the operational range available
to the operator during heatup and
cooldown of the plant, especially when
considering requirements in the closure
head flange and the vessel flange
regions. Implementing the P–T curves
that use Klc material fracture toughness
without exempting the flange
requirement of 10 CFR part 50,
Appendix G, would place a restricted
E:\FR\FM\18MRN1.SGM
18MRN1
Agencies
[Federal Register Volume 70, Number 52 (Friday, March 18, 2005)]
[Notices]
[Page 13215]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 05-5365]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-348 and 50-364]
Southern Nuclear Operating Company, Inc (SNC), Joseph M. Farley
Nuclear Power Plant, Units 1 and 2; Notice of Availability of the Final
Supplement 18 to the Generic Environmental Impact Statement for the
License Renewal of Joseph M. Farley Nuclear Power Plant, Units 1 and 2
Notice is hereby given that the U.S. Nuclear Regulatory Commission
(the Commission) has published a final plant-specific supplement to the
Generic Environmental Impact Statement (GEIS), NUREG-1437, regarding
the renewal of operating licenses NPF-2 and NPF-8 for an additional 20
years of operation at Joseph M. Farley Nuclear Power Plant (FNP). FNP
is located in Houston County, Alabama, approximately 16.5 miles east of
the City of Dothan, Alabama. Possible alternatives to the proposed
action (license renewal) include no action and reasonable alternative
energy sources.
Section 9.3 of the final supplement 18 states:
Based on: (1) The analysis and findings in the GEIS (NRC 1996;
1999), (2) the environmental report submitted by SNC (SNC 2003), (3)
consultation with Federal, State, Tribal, and local agencies, (4)
the staff's own independent review, and (5) the staff's
consideration of public comments, the recommendation of the staff is
that the Commission determine that the adverse environmental impacts
of license renewal for Farley Units 1 and 2, are not so great that
preserving the option of license renewal for energy planning
decision makers would be unreasonable.
The final Supplement 18 to the GEIS is available for public
inspection in the NRC Public Document Room (PDR) located at One White
Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, between
7:30 a.m. and 4:15 p.m. or from the Publicly Available Records (PARS)
component of NRC's Agencywide Documents Access and Management System
(ADAMS). ADAMS is accessible from the NRC's Web site at https://
www.nrc.gov/reading-rm/adams.html (the Public Electronic Reading Room).
Persons who do not have access to ADAMS, or who encounter problems in
accessing the documents located in ADAMS, should contact the PDR
reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to
pdr@nrc.gov. In addition, the Houston Love Memorial Library, 212 West
Burdeshaw Street, Dothan, Alabama, and the Lucy Maddox Memorial
Library, 11880 Columbia Street, Blakely, Georgia, have agreed to make
the final plant-specific supplement to the GEIS available for public
inspection.
FOR FURTHER INFORMATION CONTACT: Mr. Jack Cushing, License Renewal and
Environmental Impacts Program, Division of Regulatory Improvement
Programs, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Mr.
Cushing may be contacted at 301-415-1424 or via e-mail at JXC9@nrc.gov.
Dated in Rockville, Maryland, this 9th day of March, 2005.
For the Nuclear Regulatory Commission.
Pao-Tsin Kuo,
Program Director, License Renewal and Environmental Impacts Program,
Division of Regulatory Improvement Programs, Office of Nuclear Reactor
Regulation.
[FR Doc. 05-5365 Filed 3-17-05; 8:45 am]
BILLING CODE 7590-01-P