Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear Plant, Units 1 and 2, 4983-4984 [2014-01880]
Download as PDF
Federal Register / Vol. 79, No. 20 / Thursday, January 30, 2014 / Notices
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–321, 50–366; NRC–2008–
0585]
Southern Nuclear Operating Company,
Inc.; Edwin I. Hatch Nuclear Plant,
Units 1 and 2
Nuclear Regulatory
Commission.
ACTION: Environmental assessment and
finding of no significant impact;
issuance.
AGENCY:
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an exemption from its
regulations for Renewed Facility
Operating License Nos. NPF–5 and
DPR–57, issued to Southern Nuclear
Operating Company (SNC), for
operation of the Edwin I. Hatch Nuclear
Plant, Units 1 and 2 (HNP), located in
Appling County, Georgia. Based on the
results of the environmental assessment,
the NRC is issuing a finding of no
significant impact.
ADDRESSES: Please refer to Docket ID
NRC–2008–0585 when contacting the
NRC about the availability of
information regarding this document.
You may access publicly-available
information related to this action by the
following methods:
• Federal rulemaking Web site: Go to
https://www.regulations.gov and search
for Docket ID NRC–2008–0585. Address
questions about NRC dockets to Carol
Gallagher; telephone: 301–287–3422;
email: Carol.Gallagher@nrc.gov. For
technical questions, contact the
individual(s) listed in the FOR FURTHER
INFORMATION CONTACT section of this
document.
• NRC’s Agencywide Documents
Access and Management System
(ADAMS): You may access publicly
available documents online in the NRC
Library at https://www.nrc.gov/readingrm/adams.html. To begin the search,
select ‘‘ADAMS Public Documents’’ and
then select ‘‘Begin Web-based ADAMS
Search.’’ For problems with ADAMS,
please contact the NRC’s Public
Document Room (PDR) reference staff at
1–800–397–4209, 301–415–4737, or by
email to pdr.resource@nrc.gov. The
ADAMS accession number for each
document referenced in this notice (if
that document is available in ADAMS)
is provided the first time that a
document is referenced. Proposed
Exemption to 10 CFR 50.46 and 10 CFR
Part 50, Appendix K to Allow GNFZiron Fuel Cladding, dated April 23,
2013, is available in ADAMS under
Accession No. ML13115A480.
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SUMMARY:
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• NRC’s PDR: You may examine and
purchase copies of public documents at
the NRC’s PDR, Room O1–F21, One
White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT:
Robert E. Martin, Office of Nuclear
Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington,
DC 20555–0001, telephone: 301–415–
1493; email: Robert.Martin@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering issuance of an
exemption from 10 CFR 50.46 of Title
10 of the Code of Federal Regulations
(10 CFR) for Renewed Facility Operating
License Nos. NPF–5 and DPR–57, issued
to Southern Nuclear Operating
Company (SNC), for operation of the
Edwin I. Hatch Nuclear Plant, Units 1
and 2 (HNP), located in Appling
County, Georgia. Therefore, as required
by 10 CFR 51.21, the NRC performed an
environmental assessment. Based on the
results of the environmental assessment,
the NRC is issuing a finding of no
significant impact.
II. Environmental Assessment
Identification of the Proposed Action
The proposed action would allow the
use of Ziron fuel cladding in two GE14
lead test fuel assemblies (LTAs) in
either HNP, Unit 1 or Unit 2, for one or
more additional fuel cycles, up to the
standard GE14 peak pellet exposure
limit. The proposed action is described
in the licensee’s application dated April
23, 2013. The proposed action is similar
to an action previously approved by the
NRC staff (staff) wherein, on November
7, 2008 (ADAMS Accession No.
ML082950149), the NRC staff issued an
exemption enabling the use of two GE14
LTAs in Unit 2 of the HNP for fuel
cycles 21, 22 and 23. The
Environmental Assessment and Finding
of No Significant Impact for that action
was published in the Federal Register
on November 3, 2008 (73 FR 65415).
Subsequently, SNC decided not to use
those LTAs in Hatch Unit 2 cycle 23.
SNC now wishes to continue with
irradiation of the two LTAs up to the
standard GE14 peak pellet exposure
limit, and since the exemption of
November 7, 2008, specifically
addressed only HNP Unit 2 in fuel
cycles 21, 22 and 23, SNC must apply
for a further exemption to enable further
irradiation of the two LTAs in either of
the HNP reactors for one or more
additional cycles, up to GNF’s approved
peak pellet exposure.
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4983
The Need for the Proposed Action
The proposed action would allow the
use of two LTAs that will include some
fuel rods manufactured with a cladding
material, called GNF-Ziron, which is
similar in composition to Zircaloy-2, but
contains a slightly higher iron content
than specified in ASTM B350.
Irradiation of LTAs with GNF-Ziron fuel
rods will enable SNC to acquire inreactor operating experience with this
material. Pursuant to 10 CFR 50.12,
‘‘Specific exemptions,’’ the licensee has
requested an exemption from 10 CFR
50.46, ‘‘Acceptance criteria for
emergency core cooling systems for
light-water nuclear power reactors,’’ that
requires, among other items, that
‘‘[e]ach boiling or pressurized lightwater nuclear power reactor fueled with
uranium oxide pellets within
cylindrical zircaloy or ZIRLO cladding
must be provided with an emergency
core cooling system (ECCS) that must be
designed so that its calculated cooling
performance following postulated lossof-coolant accidents conforms to the
criteria set forth in paragraph (b) of this
section.’’ Appendix K to 10 CFR Part 50,
‘‘ECCS Evaluation Models,’’ requires,
among other items, that the rate of
energy release, hydrogen generation,
and cladding oxidation from the metal/
water reaction shall be calculated using
the Baker-Just equation. The regulations
at 10 CFR 50.46 and 10 CFR Part 50,
Appendix K, make no provisions for use
of fuel rods clad in a material other than
zircaloy or ZIRLO. The proposed action
would allow the licensee to irradiate a
small number of LTAs using fuel rods
clad with Ziron alloy either in HNP Unit
1 or Unit 2 up to the standard GE14
peak pellet exposure. Since the material
specifications of the Ziron alloy differ
from the specification for zircaloy or
ZIRLO, a plant-specific exemption is
required to support the use of the LTAs.
Environmental Impacts of the Proposed
Action
The NRC has completed its safety
evaluation of the proposed action and
concludes that the application of 10
CFR 50.46 and Appendix K to 10 CFR
Part 50, is not necessary to achieve the
underlying purpose of the rule.
The details of the NRC staff safety
evaluation will be provided in the
exemption issued as part of the letter to
the licensee approving the exemption to
the regulations.
The staff has concluded that such a
change would not adversely affect plant
safety, and would have no adverse effect
on the probability of any accident. For
accidents that involve damage or
melting of the fuel in the reactor core,
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4984
Federal Register / Vol. 79, No. 20 / Thursday, January 30, 2014 / Notices
the fuel rod integrity of GNF-Ziron
cladded fuel has been shown to be
similar to zircaloy cladded fuel;
therefore, the consequences of an
accident will not be affected. For
accidents in which the core remains
intact, the use of GNF-Ziron cladding
will not have a significant effect on the
mix of fission products that could be
released in the event of a serious
accident; thus, the previously analyzed
accident dose consequences remain
bounding. Regulatory limits on
radiological effluent releases are
independent of the type of fuel cladding
used. The requirements of 10 CFR
50.36a, Appendix I to 10 CFR Part 50,
and 40 CFR Part 190, as well as the
plant’s Technical Specifications ensure
that the release of radioactive gaseous,
liquid, and solid waste to unrestricted
areas are kept to ‘‘as low as is
reasonably achievable’’ (ALARA) levels.
The licensee’s radioactive waste
processing system will collect, control,
process to reduce the amount of
radioactivity, and discharge the waste in
accordance with regulatory limits.
Therefore, the NRC staff concluded that
during routine operations, there will be
no significant increase of radiological
effluents released into the environment
as a result of the proposed exemption
request. No significant increase in the
allowable individual occupational
radiation exposure will occur. The
impact to workers is not expected to
change because radiation exposure will
be controlled in accordance with the
licensee’s radiation protection program,
the ALARA program, in-plant shielding,
the use of temporary shielding, and
engineering controls. The use of GNFZiron fuel rods will not change the
potential environmental impacts of
incident-free transportation of spent
nuclear fuel provided the shipping
casks are maintained and transported
within the Department of
Transportation and NRC’s regulations.
Therefore, there are no significant
radiological environmental impacts
associated with the proposed action.
With regard to potential nonradiological impacts, the proposed
action would not change the types or
amounts of non-radiological plant
effluents. Therefore the proposed action
would not result in any foreseeable
impacts to land, air, or water resources,
including impacts to biota because there
would be no change in effluents or
emissions into the environment. In
addition, there are no known
socioeconomic or environmental justice
impacts associated with such proposed
action because there would be no
increase or change in effluents or
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18:24 Jan 29, 2014
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emissions into the environment that
would disproportionately or adversely
affect the minority or low income
populations. Therefore, there are no
significant non-radiological
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
previously considered in NUREG–1437,
Supplement 4, ‘‘Generic Environmental
Impact Statement for License Renewal
of Nuclear Plants, regarding the Edwin
I. Hatch Nuclear Plant, Units 1 and 2,
dated May 31, 2001.
Agencies and Persons Consulted
On August 13, 2013, the NRC staff
notified the State official of Georgia, Mr.
Chuck Mueller, of the Department of
Natural Resources, regarding the
environmental impact of the proposed
action. The State official had no
comments.
III. 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 April 23, 2013.
Dated at Rockville, Maryland, this 23rd day
of January, 2014.
For the Nuclear Regulatory Commission.
Robert Pascarelli,
Chief, Plant Licensing Branch II–1, Division
of Operating Reactor Licensing, Office of
Nuclear Reactor Regulation.
[FR Doc. 2014–01880 Filed 1–29–14; 8:45 am]
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NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS); Meeting of the
ACRS Subcommittee on Planning and
Procedures
Notice of Meeting
The ACRS Subcommittee on Planning
and Procedures will hold a meeting on
February 4, 2014, Room T–2B3, 11545
Rockville Pike, Rockville, Maryland.
The meeting will be open to public
attendance with the exception of a
portion that may be closed pursuant to
5 U.S.C. 552b(c)(2) and (6) to discuss
organizational and personnel matters
that relate solely to the internal
personnel rules and practices of the
ACRS, and information the release of
which would constitute a clearly
unwarranted invasion of personal
privacy.
The agenda for the subject meeting
shall be as follows:
Tuesday, February 4, 2014–12:00 p.m.
Until 1:00 p.m.
The Subcommittee will discuss
proposed ACRS activities and related
matters. The Subcommittee will gather
information, analyze relevant issues and
facts, and formulate proposed positions
and actions, as appropriate, for
deliberation by the Full Committee.
Members of the public desiring to
provide oral statements and/or written
comments should notify the Designated
Federal Official (DFO), Quynh Nguyen
(Telephone 301–415–5844 or Email:
Quynh.Nguyen@nrc.gov) five days prior
to the meeting, if possible, so that
arrangements can be made. Thirty-five
hard copies of each presentation or
handout should be provided to the DFO
thirty minutes before the meeting. In
addition, one electronic copy of each
presentation should be emailed to the
DFO one day before the meeting. If an
electronic copy cannot be provided
within this timeframe, presenters
should provide the DFO with a CD
containing each presentation at least
thirty minutes before the meeting.
Electronic recordings will be permitted
only during those portions of the
meeting that are open to the public.
Detailed procedures for the conduct of
and participation in ACRS meetings
were published in the Federal Register
on November 8, 2013 (78 CFR 67205–
67206).
Information regarding changes to the
agenda, whether the meeting has been
canceled or rescheduled, and the time
allotted to present oral statements can
be obtained by contacting the identified
DFO. Moreover, in view of the
E:\FR\FM\30JAN1.SGM
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Agencies
[Federal Register Volume 79, Number 20 (Thursday, January 30, 2014)]
[Notices]
[Pages 4983-4984]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-01880]
[[Page 4983]]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-321, 50-366; NRC-2008-0585]
Southern Nuclear Operating Company, Inc.; Edwin I. Hatch Nuclear
Plant, Units 1 and 2
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact;
issuance.
-----------------------------------------------------------------------
SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an exemption from its regulations for Renewed Facility
Operating License Nos. NPF-5 and DPR-57, issued to Southern Nuclear
Operating Company (SNC), for operation of the Edwin I. Hatch Nuclear
Plant, Units 1 and 2 (HNP), located in Appling County, Georgia. Based
on the results of the environmental assessment, the NRC is issuing a
finding of no significant impact.
ADDRESSES: Please refer to Docket ID NRC-2008-0585 when contacting the
NRC about the availability of information regarding this document. You
may access publicly-available information related to this action by the
following methods:
Federal rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2008-0585. Address
questions about NRC dockets to Carol Gallagher; telephone: 301-287-
3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact
the individual(s) listed in the FOR FURTHER INFORMATION CONTACT section
of this document.
NRC's Agencywide Documents Access and Management System
(ADAMS): You may access publicly available documents online in the NRC
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number
for each document referenced in this notice (if that document is
available in ADAMS) is provided the first time that a document is
referenced. Proposed Exemption to 10 CFR 50.46 and 10 CFR Part 50,
Appendix K to Allow GNF-Ziron Fuel Cladding, dated April 23, 2013, is
available in ADAMS under Accession No. ML13115A480.
NRC's PDR: You may examine and purchase copies of public
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852.
FOR FURTHER INFORMATION CONTACT: Robert E. Martin, Office of Nuclear
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, telephone: 301-415-1493; email: Robert.Martin@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The NRC is considering issuance of an exemption from 10 CFR 50.46
of Title 10 of the Code of Federal Regulations (10 CFR) for Renewed
Facility Operating License Nos. NPF-5 and DPR-57, issued to Southern
Nuclear Operating Company (SNC), for operation of the Edwin I. Hatch
Nuclear Plant, Units 1 and 2 (HNP), located in Appling County, Georgia.
Therefore, as required by 10 CFR 51.21, the NRC performed an
environmental assessment. Based on the results of the environmental
assessment, the NRC is issuing a finding of no significant impact.
II. Environmental Assessment
Identification of the Proposed Action
The proposed action would allow the use of Ziron fuel cladding in
two GE14 lead test fuel assemblies (LTAs) in either HNP, Unit 1 or Unit
2, for one or more additional fuel cycles, up to the standard GE14 peak
pellet exposure limit. The proposed action is described in the
licensee's application dated April 23, 2013. The proposed action is
similar to an action previously approved by the NRC staff (staff)
wherein, on November 7, 2008 (ADAMS Accession No. ML082950149), the NRC
staff issued an exemption enabling the use of two GE14 LTAs in Unit 2
of the HNP for fuel cycles 21, 22 and 23. The Environmental Assessment
and Finding of No Significant Impact for that action was published in
the Federal Register on November 3, 2008 (73 FR 65415). Subsequently,
SNC decided not to use those LTAs in Hatch Unit 2 cycle 23. SNC now
wishes to continue with irradiation of the two LTAs up to the standard
GE14 peak pellet exposure limit, and since the exemption of November 7,
2008, specifically addressed only HNP Unit 2 in fuel cycles 21, 22 and
23, SNC must apply for a further exemption to enable further
irradiation of the two LTAs in either of the HNP reactors for one or
more additional cycles, up to GNF's approved peak pellet exposure.
The Need for the Proposed Action
The proposed action would allow the use of two LTAs that will
include some fuel rods manufactured with a cladding material, called
GNF-Ziron, which is similar in composition to Zircaloy-2, but contains
a slightly higher iron content than specified in ASTM B350. Irradiation
of LTAs with GNF-Ziron fuel rods will enable SNC to acquire in-reactor
operating experience with this material. Pursuant to 10 CFR 50.12,
``Specific exemptions,'' the licensee has requested an exemption from
10 CFR 50.46, ``Acceptance criteria for emergency core cooling systems
for light-water nuclear power reactors,'' that requires, among other
items, that ``[e]ach boiling or pressurized light-water nuclear power
reactor fueled with uranium oxide pellets within cylindrical zircaloy
or ZIRLO cladding must be provided with an emergency core cooling
system (ECCS) that must be designed so that its calculated cooling
performance following postulated loss-of-coolant accidents conforms to
the criteria set forth in paragraph (b) of this section.'' Appendix K
to 10 CFR Part 50, ``ECCS Evaluation Models,'' requires, among other
items, that the rate of energy release, hydrogen generation, and
cladding oxidation from the metal/water reaction shall be calculated
using the Baker-Just equation. The regulations at 10 CFR 50.46 and 10
CFR Part 50, Appendix K, make no provisions for use of fuel rods clad
in a material other than zircaloy or ZIRLO. The proposed action would
allow the licensee to irradiate a small number of LTAs using fuel rods
clad with Ziron alloy either in HNP Unit 1 or Unit 2 up to the standard
GE14 peak pellet exposure. Since the material specifications of the
Ziron alloy differ from the specification for zircaloy or ZIRLO, a
plant-specific exemption is required to support the use of the LTAs.
Environmental Impacts of the Proposed Action
The NRC has completed its safety evaluation of the proposed action
and concludes that the application of 10 CFR 50.46 and Appendix K to 10
CFR Part 50, is not necessary to achieve the underlying purpose of the
rule.
The details of the NRC staff safety evaluation will be provided in
the exemption issued as part of the letter to the licensee approving
the exemption to the regulations.
The staff has concluded that such a change would not adversely
affect plant safety, and would have no adverse effect on the
probability of any accident. For accidents that involve damage or
melting of the fuel in the reactor core,
[[Page 4984]]
the fuel rod integrity of GNF-Ziron cladded fuel has been shown to be
similar to zircaloy cladded fuel; therefore, the consequences of an
accident will not be affected. For accidents in which the core remains
intact, the use of GNF-Ziron cladding will not have a significant
effect on the mix of fission products that could be released in the
event of a serious accident; thus, the previously analyzed accident
dose consequences remain bounding. Regulatory limits on radiological
effluent releases are independent of the type of fuel cladding used.
The requirements of 10 CFR 50.36a, Appendix I to 10 CFR Part 50, and 40
CFR Part 190, as well as the plant's Technical Specifications ensure
that the release of radioactive gaseous, liquid, and solid waste to
unrestricted areas are kept to ``as low as is reasonably achievable''
(ALARA) levels. The licensee's radioactive waste processing system will
collect, control, process to reduce the amount of radioactivity, and
discharge the waste in accordance with regulatory limits. Therefore,
the NRC staff concluded that during routine operations, there will be
no significant increase of radiological effluents released into the
environment as a result of the proposed exemption request. No
significant increase in the allowable individual occupational radiation
exposure will occur. The impact to workers is not expected to change
because radiation exposure will be controlled in accordance with the
licensee's radiation protection program, the ALARA program, in-plant
shielding, the use of temporary shielding, and engineering controls.
The use of GNF-Ziron fuel rods will not change the potential
environmental impacts of incident-free transportation of spent nuclear
fuel provided the shipping casks are maintained and transported within
the Department of Transportation and NRC's regulations. Therefore,
there are no significant radiological environmental impacts associated
with the proposed action.
With regard to potential non-radiological impacts, the proposed
action would not change the types or amounts of non-radiological plant
effluents. Therefore the proposed action would not result in any
foreseeable impacts to land, air, or water resources, including impacts
to biota because there would be no change in effluents or emissions
into the environment. In addition, there are no known socioeconomic or
environmental justice impacts associated with such proposed action
because there would be no increase or change in effluents or emissions
into the environment that would disproportionately or adversely affect
the minority or low income populations. Therefore, there are no
significant non-radiological 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 previously considered in NUREG-1437, Supplement 4, ``Generic
Environmental Impact Statement for License Renewal of Nuclear Plants,
regarding the Edwin I. Hatch Nuclear Plant, Units 1 and 2, dated May
31, 2001.
Agencies and Persons Consulted
On August 13, 2013, the NRC staff notified the State official of
Georgia, Mr. Chuck Mueller, of the Department of Natural Resources,
regarding the environmental impact of the proposed action. The State
official had no comments.
III. 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 April 23, 2013.
Dated at Rockville, Maryland, this 23rd day of January, 2014.
For the Nuclear Regulatory Commission.
Robert Pascarelli,
Chief, Plant Licensing Branch II-1, Division of Operating Reactor
Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2014-01880 Filed 1-29-14; 8:45 am]
BILLING CODE 7590-01-P