Southern Nuclear Operating Company, Inc., Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2; Environmental Assessment and Finding of No Significant Impact, 76082-76083 [E5-7704]
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Federal Register / Vol. 70, No. 245 / Thursday, December 22, 2005 / Notices
same time. The amendments shall be
issued and made effective at the time
the proposed direct license transfers are
completed.
It is further ordered that FENOC shall
inform the Director of the Office of
Nuclear Reactor Regulation in writing of
the date of closing of the transfer of the
Penn Power, Cleveland Electric, Ohio
Edison, OES Nuclear, and Toledo
Edison interests in BVPS 1, BVPS 2,
Davis-Besse, and Perry no later than 5
business days prior to closing. Should
the transfer of the licenses not be
completed by December 31, 2006, this
Order shall become null and void,
provided; however, that upon written
application and for good cause shown,
such date may be extended by order.
This Order supercedes the Order
issued on November 15, 2005, and is
effective as of December 16, 2005.
For further details with respect to this
Order, see the initial applications dated
May 18 and June 1, 2005, as
supplemented by letters dated July 15
and October 31, 2005, and the revised
non-proprietary safety evaluation dated
December 16, 2005, which are available
for public inspection at the
Commission’s Public Document Room
(PDR), located at One White Flint North,
Public File Area 01 F21, 11555
Rockville Pike (first floor), Rockville,
Maryland and accessible electronically
from the Agencywide Documents
Access and Management System
(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, 301–415–4737, or
by e-mail to pdr@nrc.gov.
Dated at Rockville, Maryland this 16th day
of December 2005.
For The Nuclear Regulatory Commission.
J.E. Dyer,
Director, Office of Nuclear Reactor
Regulation.
[FR Doc. E5–7723 Filed 12–21–05; 8:45 am]
cchase on PROD1PC60 with NOTICES
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–321 and 50–366]
Southern Nuclear Operating Company,
Inc., Edwin I. Hatch Nuclear Plant, Unit
Nos. 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, section
50.55a(b)(2)(ix)(G), for Facility
Operating License Nos. DRP–57 and
NPF–5, issued to Southern Nuclear
Operating Company, Inc. (the licensee),
for operation of the Edwin I. Hatch
Nuclear Plant, Unit Nos. 1 and 2
(Hatch), located in Appling County,
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 50.55a(b)(2)(ix)(G) and allow the
licensee to perform a general visual
examination of the accessible surface
areas of the containment vessel pressure
retaining vent system, in lieu of the VT–
3 examination required by 10 CFR.
The proposed action is in accordance
with the licensee’s application dated
March 30, 2005, as supplemented by
letters dated August 2 and 24, 2005.
The Need for the Proposed Action
During the 3rd 10-year inservice
inspection (ISI) interval, which ends
December 31, 2005, the licensee’s code
of record, the 1992 American Society of
Mechanical Engineers, Boiler and
Pressure Vessel Code (ASME Code),
including the 1992 addenda, required a
VT–3 examination of the accessible
surface areas of the boiling water reactor
(BWR) vent system. For the 3rd 10-year
ISI interval, by letter dated July 19,
2000, the licensee requested in Relief
Request RR–MC–9 to perform a general
visual examination in lieu of the VT–3
examination. The licensee explained
that the proposed alternative was
sufficient to detect the types of
corrosion expected in the BWR vent
system. This request was approved by
the NRC by letter dated October 4, 2000.
For the 4th 10-year ISI interval, the
licensee’s code of record will be the 2001
edition through the 2003 addenda of the
ASME Code. Modifications to the ASME
Code and 10 CFR 50.55a have relocated the
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16:55 Dec 21, 2005
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requirement to perform the VT–3
examination from the ASME Code to 10 CFR
50.55a(b)(2)(ix)(G). The licensee believes that
the examination provisions previously
authorized through Relief Request RR–MC–9
have proven to be sufficient to maintain the
structural integrity and leak-tightness of the
containment surfaces, and, therefore, serve
the underlying purpose of the rule. The
licensee is requesting to continue the use of
similar provisions during the 4th ISI interval
through an exemption.
Environmental Impacts of the Proposed
Action
The NRC has completed its safety
evaluation of the proposed action and
concludes that performing a general
visual examination as part of
maintaining the integrity of the coating
system will ensure the integrity of the
coated vent system components,
providing an acceptable level of quality
and safety.
The details of the NRC staff’s safety
evaluation will be provided in the
exemption that will be issued as part of
the letter to the licensee approving the
exemption from the regulation.
The proposed action will not
significantly increase the probability or
consequences of accidents. No changes
are being made in the types of effluents
that may be released off site. There is no
significant increase in the amount of
any effluent released off site. There is no
significant increase in occupational or
public radiation exposure. Therefore,
there are no significant radiological
environmental impacts associated with
the proposed action.
With regard to potential
nonradiological impacts, the proposed
action does not have a potential to affect
any historic sites. It does not affect
nonradiological plant effluents and has
no other environmental impact.
Therefore, there are no significant
nonradiological environmental impacts
associated with the proposed action.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action.
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
action, the staff considered denial of the
proposed action (i.e., the ‘‘no-action’’
alternative). Denial of the application
would result in no change in current
environmental impacts. The
environmental impacts of the proposed
action and the alternative action are
similar.
Alternative Use of Resources
The action does not involve the use of
any different resources than those
E:\FR\FM\22DEN1.SGM
22DEN1
Federal Register / Vol. 70, No. 245 / Thursday, December 22, 2005 / Notices
previously considered in the ‘‘Final
Environmental Statement Related to the
Operation of the Edwin I. Hatch Nuclear
Plant, Unit 1 and Unit 2,’’ dated October
1972, and NUREG–0417, ‘‘Final
Environmental Statement Related to the
Operation of the Edwin I. Hatch Nuclear
Plant, Unit 2,’’ dated March 1978.
Agencies and Persons Consulted
In accordance with its stated policy,
on November 30, 2005, the staff
consulted with the Georgia State
official, James Hardeman, of the
Department of Natural Resources,
regarding the environmental impact of
the proposed action for Hatch. The State
official had no comments.
Finding of No Significant Impact
On the basis of the environmental
assessment, the NRC concludes that the
proposed action will not have a
significant effect on the quality of the
human environment. Accordingly, the
NRC has determined not to prepare an
environmental impact statement for the
proposed action.
For further details with respect to the
proposed action, see the licensee’s letter
dated March 30, 2005, as supplemented
by letters dated August 2 and 24, 2005.
Documents may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room (PDR), located at One
White Flint North, 11555 Rockville Pike
(first floor), Rockville, Maryland.
Publicly available records will be
accessible electronically from the
Agencywide Documents Access and
Management System (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 send an
e-mail to pdr@nrc.gov.
cchase on PROD1PC60 with NOTICES
Dated at Rockville, Maryland, this 14th day
of December 2004.
For the Nuclear Regulatory Commission.
Christopher Gratton,
Sr. Project Manager, Plant Licensing Branch
II–1, Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. E5–7704 Filed 12–21–05; 8:45 am]
BILLING CODE 7590–01–P
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Proposed Generic Communication
Post-Fire Safe-Shutdown Circuit
Analysis Spurious Actuations
Nuclear Regulatory
Commission (NRC).
ACTION: Notice of opportunity for public
comment. Reopening of comment
period.
AGENCY:
SUMMARY: On October 19, 2005 (70 FR
60859), the NRC published for public
comment a generic letter (GL) to:
(1) Request addressees to review their
fire protection program to confirm
compliance with existing applicable
regulatory requirements regarding their
assumptions of the phrase ‘‘one-at-atime’’ in light of the information
provided in this GL and, if appropriate,
take additional actions to return to
compliance. Specifically, although some
licensees have performed their post-fire,
safe-shutdown circuit analyses based on
an assumption of only a single spurious
actuation per fire event or that spurious
actuations will occur ‘‘one-at-a-time,’’
recent industry cable fire test results
demonstrated that these assumptions
are not valid.
(2) Require addressees to submit a
written response to the NRC in
accordance with NRC regulations in
Title 10 of the Code of Federal
Regulations (10 CFR) Section 50.54(f).
The Nuclear Energy Institute (NEI)
has requested a 45-day extension of the
comment period. NEI believes that
additional time will be needed to
provide appropriate comments on the
draft GL. NEI based its request on the
time needed to perform an assessment
of the safety significance of multiple
sequential and cumulative failures; an
evaluation of the industry test results
and interviews with the industry project
team; an evaluation of the NUREG/CR–
6776, and an assessment of the NRC/
licensee documentation associated with
the prior NRC staff positions and
practices related to safe-shutdown
circuit analysis. The NRC has decided to
reopen the comment period for an
additional 45 days.
This Federal Register notice is
available through the NRC’s
Agencywide Documents Access and
Management System (ADAMS) under
accession number ML051650017.
DATES: The comment period has been
extended and now expires February 6,
2006. Comments submitted after this
date will be considered if it is practical
to do so, but assurance of consideration
cannot be given except for comments
received on or before this date.
Frm 00065
Fmt 4703
Sfmt 4703
Submit written comments
to the Chief, Rules and Directives
Branch, Division of Administrative
Services, Office of Administration, U.S.
Nuclear Regulatory Commission, Mail
Stop T6–D59, Washington, DC 20555–
0001, and cite the publication date and
page number of this Federal Register
notice. Written comments may also be
delivered to NRC Headquarters, 11545
Rockville Pike (Room T–6D59),
Rockville, Maryland, between 7:30 am
and 4:15 pm on Federal workdays.
FOR FURTHER INFORMATION CONTACT:
Robert Wolfgang at 301–415–1624 or by
e-mail: rjw1@nrc.gov.
Documents may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room at One White Flint
North, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available
records will be accessible electronically
from the Agencywide Documents
Access and Management System
(ADAMS) Public Electronic Reading
Room on the Internet at the NRC Web
site, https://www.nrc.gov/NRC/ADAMS/
index.html. If you do not have access to
ADAMS or if you have problems in
accessing the documents in ADAMS,
contact the NRC Public Document Room
(PDR) reference staff at 1–800–397–4209
or 301–415–4737 or by e-mail to
pdr@nrc.gov.
ADDRESSEES:
NUCLEAR REGULATORY
COMMISSION
PO 00000
76083
Dated at Rockville, Maryland, this Friday
the 16th day of December 2005.
For the Nuclear Regulatory Commission.
Christopher I. Grimes,
Division of Policy and Rulemaking, Office
of Nuclear Reactor Regulation.
[FR Doc. E5–7702 Filed 12–21–05; 8:45 am]
BILLING CODE 7590–01–P
SECURITIES AND EXCHANGE
COMMISSION
Proposed Collection; Comment
Request
Upon Written Request, Copies Available
from: Securities and Exchange
Commission, Office of Filings and
Information Services, Washington, DC
20549.
Extension:
Rule 12f–1; SEC File No. 270–139; OMB
Control No. 3235–0128.
Notice is hereby given that pursuant
to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.), the Securities
and Exchange Commission
(‘‘Commission’’) is soliciting comments
on the collection of information
summarized below. The Commission
plans to submit the existing collection
of information to the Office of
E:\FR\FM\22DEN1.SGM
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]]>Agencies
[Federal Register Volume 70, Number 245 (Thursday, December 22, 2005)]
[Notices]
[Pages 76082-76083]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-7704]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-321 and 50-366]
Southern Nuclear Operating Company, Inc., Edwin I. Hatch Nuclear
Plant, Unit Nos. 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, section 50.55a(b)(2)(ix)(G), for
Facility Operating License Nos. DRP-57 and NPF-5, issued to Southern
Nuclear Operating Company, Inc. (the licensee), for operation of the
Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2 (Hatch), located in
Appling County, 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 50.55a(b)(2)(ix)(G) and allow the licensee to perform a
general visual examination of the accessible surface areas of the
containment vessel pressure retaining vent system, in lieu of the VT-3
examination required by 10 CFR.
The proposed action is in accordance with the licensee's
application dated March 30, 2005, as supplemented by letters dated
August 2 and 24, 2005.
The Need for the Proposed Action
During the 3rd 10-year inservice inspection (ISI) interval, which
ends December 31, 2005, the licensee's code of record, the 1992
American Society of Mechanical Engineers, Boiler and Pressure Vessel
Code (ASME Code), including the 1992 addenda, required a VT-3
examination of the accessible surface areas of the boiling water
reactor (BWR) vent system. For the 3rd 10-year ISI interval, by letter
dated July 19, 2000, the licensee requested in Relief Request RR-MC-9
to perform a general visual examination in lieu of the VT-3
examination. The licensee explained that the proposed alternative was
sufficient to detect the types of corrosion expected in the BWR vent
system. This request was approved by the NRC by letter dated October 4,
2000.
For the 4th 10-year ISI interval, the licensee's code of record
will be the 2001 edition through the 2003 addenda of the ASME Code.
Modifications to the ASME Code and 10 CFR 50.55a have relocated the
requirement to perform the VT-3 examination from the ASME Code to 10
CFR 50.55a(b)(2)(ix)(G). The licensee believes that the examination
provisions previously authorized through Relief Request RR-MC-9 have
proven to be sufficient to maintain the structural integrity and
leak-tightness of the containment surfaces, and, therefore, serve
the underlying purpose of the rule. The licensee is requesting to
continue the use of similar provisions during the 4th ISI interval
through an exemption.
Environmental Impacts of the Proposed Action
The NRC has completed its safety evaluation of the proposed action
and concludes that performing a general visual examination as part of
maintaining the integrity of the coating system will ensure the
integrity of the coated vent system components, providing an acceptable
level of quality and safety.
The details of the NRC staff's safety evaluation will be provided
in the exemption that will be issued as part of the letter to the
licensee approving the exemption from the regulation.
The proposed action will not significantly increase the probability
or consequences of accidents. No changes are being made in the types of
effluents that may be released off site. There is no significant
increase in the amount of any effluent released off site. There is no
significant increase in occupational or public radiation exposure.
Therefore, there are no significant radiological environmental impacts
associated with the proposed action.
With regard to potential nonradiological impacts, the proposed
action does not have a potential to affect any historic sites. It does
not affect nonradiological plant effluents and has no other
environmental impact. Therefore, there are no significant
nonradiological environmental impacts associated with the proposed
action.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to the proposed action, the staff considered
denial of the proposed action (i.e., the ``no-action'' alternative).
Denial of the application would result in no change in current
environmental impacts. The environmental impacts of the proposed action
and the alternative action are similar.
Alternative Use of Resources
The action does not involve the use of any different resources than
those
[[Page 76083]]
previously considered in the ``Final Environmental Statement Related to
the Operation of the Edwin I. Hatch Nuclear Plant, Unit 1 and Unit 2,''
dated October 1972, and NUREG-0417, ``Final Environmental Statement
Related to the Operation of the Edwin I. Hatch Nuclear Plant, Unit 2,''
dated March 1978.
Agencies and Persons Consulted
In accordance with its stated policy, on November 30, 2005, the
staff consulted with the Georgia State official, James Hardeman, of the
Department of Natural Resources, regarding the environmental impact of
the proposed action for Hatch. The State official had no comments.
Finding of No Significant Impact
On the basis of the environmental assessment, the NRC concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the NRC has determined
not to prepare an environmental impact statement for the proposed
action.
For further details with respect to the proposed action, see the
licensee's letter dated March 30, 2005, as supplemented by letters
dated August 2 and 24, 2005. Documents may be examined, and/or copied
for a fee, at the NRC's Public Document Room (PDR), located at One
White Flint North, 11555 Rockville Pike (first floor), Rockville,
Maryland. Publicly available records will be accessible electronically
from the Agencywide Documents Access and Management System (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 send an e-mail to
pdr@nrc.gov.
Dated at Rockville, Maryland, this 14th day of December 2004.
For the Nuclear Regulatory Commission.
Christopher Gratton,
Sr. Project Manager, Plant Licensing Branch II-1, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E5-7704 Filed 12-21-05; 8:45 am]
BILLING CODE 7590-01-P
