Omaha Public Power District, Fort Calhoun Station, Unit 1, Environmental Assessment and Finding of No Significant Impact, 10835-10836 [2010-4940]
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Federal Register / Vol. 75, No. 45 / Tuesday, March 9, 2010 / Notices
Steven’s Act are expected. There are no
impacts to the air or ambient air quality.
There are no impacts to historical and
cultural resources. There would be no
impact to socioeconomic resources.
Therefore, no changes to or different
types of non-radiological environmental
impacts are expected as a result of the
proposed exemption.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action. In addition, in promulgating its
revisions to 10 CFR part 73, the
Commission prepared an environmental
assessment and published a finding of
no significant impact [Part 73, Power
Reactor Security Requirements, 74 FR
13926 (March 27, 2009)].
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 to the
regulation, if granted.
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
actions, the NRC staff considered denial
of the proposed action (i.e., the ‘‘noaction’’ alternative). Denial of the
exemption request would result in no
change in current environmental
impacts. If the proposed action was
denied, the licensee would have to
comply with the March 31, 2010,
implementation deadline. The
environmental impacts of the proposed
exemption and the ‘‘no-action’’
alternative are similar.
dated January 27, 2010. Portions of the
document contain security-related
information and, accordingly, are not
available to the public. Other parts of
the document may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room (PDR), located at One
White Flint North, Room O–1 F21,
11555 Rockville Pike (first floor),
Rockville, Maryland 20852. 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.resource@nrc.gov.
Dated at Rockville, Maryland, this 25th day
of February 2010.
For the Nuclear Regulatory Commission.
Lynnea E. Wilkins,
Project Manager, Plant Licensing Branch IV,
Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. 2010–4676 Filed 3–8–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–285; NRC–2010–0087]
Agencies and Persons Consulted
In accordance with its stated policy,
on February 1, 2010, the NRC staff
consulted with the Washington State
official, Mr. R. Cowley of the Office of
Radiation Protection, regarding the
environmental impact of the proposed
action. The State official had no
comments.
sroberts on DSKD5P82C1PROD with NOTICES
Alternative Use of Resources
The action does not involve the use of
any different resources than those
considered in the Final Environmental
Statement for CGS dated December
1981.
The U.S. Nuclear Regulatory
Commission (NRC) is considering
issuance of an exemption, pursuant to
Title 10 of the Code of Federal
Regulations (10 CFR) Section 73.5,
‘‘Specific exemptions,’’ from the
implementation date for certain new
requirements of 10 CFR part 73,
‘‘Physical protection of plants and
materials,’’ for Renewed Facility
Operating License No. DPR–40, issued
to Omaha Public Power District (OPPD,
the licensee), for operation of Fort
Calhoun Station, Unit 1 (FCS), located
in Washington County, Nebraska.
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.
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
VerDate Nov<24>2008
19:04 Mar 08, 2010
Jkt 220001
Omaha Public Power District, Fort
Calhoun Station, Unit 1, Environmental
Assessment and Finding of No
Significant Impact
PO 00000
Frm 00082
Fmt 4703
Sfmt 4703
10835
Environmental Assessment
Identification of the Proposed Action
The proposed action would exempt
FCS from the required implementation
date of March 31, 2010, for several new
requirements of 10 CFR part 73.
Specifically, FCS would be granted an
exemption from being in full
compliance with certain new
requirements contained in 10 CFR 73.55
by the March 31, 2010, deadline. OPPD
has proposed an alternate full
compliance implementation date of
October 5, 2011, approximately 19
months beyond the date required by 10
CFR part 73. The proposed action, an
extension of the schedule for
completion of certain actions required
by the revised 10 CFR part 73, does not
involve any physical changes to the
reactor, fuel, plant structures, support
structures, water, or land at the FCS site.
The proposed action is in accordance
with the licensee’s application dated
December 31, 2009, as supplemented by
letter dated January 21, 2010.
The Need for the Proposed Action
The proposed action is needed to
provide the licensee with additional
time to perform the required upgrades to
the FCS security system due to the time
required for significant design,
procurement, and installation activities
needed to implement the required
upgrades.
Environmental Impacts of the Proposed
Action
The NRC has completed its
environmental assessment of the
proposed exemption. The staff has
concluded that the proposed action to
extend the implementation deadline
would not significantly affect plant
safety and would not have a significant
adverse effect on the probability of an
accident occurring.
The proposed action would not result
in an increased radiological hazard
beyond those previously analyzed in the
environmental assessment and finding
of no significant impact made by the
Commission in promulgating its
revisions to 10 CFR part 73 as discussed
in a Federal Register notice dated
March 27, 2009 (74 FR 13926). There
will be no change to radioactive
effluents that affect radiation exposures
to plant workers and members of the
public. Therefore, no changes or
different types of radiological impacts
are expected as a result of the proposed
exemption.
The proposed action does not result
in changes to land use or water use, or
result in changes to the quality or
quantity of non-radiological effluents.
E:\FR\FM\09MRN1.SGM
09MRN1
10836
Federal Register / Vol. 75, No. 45 / Tuesday, March 9, 2010 / Notices
No changes to the National Pollution
Discharge Elimination System permit
are needed. No effects on the aquatic or
terrestrial habitat in the vicinity of the
plant, or to threatened, endangered, or
protected species under the Endangered
Species Act, or impacts to essential fish
habitat covered by the MagnusonSteven’s Act are expected. There are no
impacts to the air or ambient air quality.
There are no impacts to historical and
cultural resources. There would be no
impact to socioeconomic resources.
Therefore, no changes to or different
types of non-radiological environmental
impacts are expected as a result of the
proposed exemption.
Accordingly, the NRC concludes that
there are no significant environmental
impacts associated with the proposed
action. In addition, in promulgating its
revisions to 10 CFR part 73, the
Commission prepared an environmental
assessment and published a finding of
no significant impact [Part 73, Power
Reactor Security Requirements, 74 FR
13926 (March 27, 2009)].
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 to the
regulation, if granted.
Environmental Impacts of the
Alternatives to the Proposed Action
As an alternative to the proposed
actions, the NRC staff considered denial
of the proposed actions (i.e., the ‘‘noaction’’ alternative). Denial of the
exemption request would result in no
change in current environmental
impacts. If the proposed action was
denied, the licensee would have to
comply with the March 31, 2010,
implementation deadline. The
environmental impacts of the proposed
exemption and the ‘‘no-action’’
alternative are similar.
sroberts on DSKD5P82C1PROD with NOTICES
Alternative Use of Resources
The action does not involve the use of
any different resources than those
considered in the Final Environmental
Statement for the FCS dated August
1972, as supplemented through the
‘‘Generic Environmental Impact
Statement for License Renewal of
Nuclear Plants: Fort Calhoun Station
Unit 1—Final Report (NUREG–1437,
Supplement 12).’’
Agencies and Persons Consulted
In accordance with its stated policy,
on February 4, 2010, the NRC staff
consulted with the Nebraska State
official, Julia Schmitt, of the Department
of Health and Human Services
Regulation and Licensure, regarding the
environmental impact of the proposed
VerDate Nov<24>2008
19:04 Mar 08, 2010
Jkt 220001
action. 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 December 31, 2009, as
supplemented by letter dated January
21, 2010. The January 21, 2010,
submittal and portions of the December
31, 2009, submittal contain securityrelated information and, accordingly,
are exempt from public disclosure.
Other parts of the December 31, 2009,
document may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room (PDR), located at One
White Flint North, Room O–1 F21,
11555 Rockville Pike (first floor),
Rockville, Maryland 20852. 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.resource@nrc.gov.
Dated at Rockville, Maryland, this 2nd day
of March 2010.
For the Nuclear Regulatory Commission.
Lynnea Wilkins,
Project Manager, Plant Licensing Branch IV,
Division of Operating Reactor Licensing,
Office of Nuclear Reactor Regulation.
[FR Doc. 2010–4940 Filed 3–8–10; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–334 And 50–412; NRC–
2010–0049]
Firstenergy Nuclear Operating
Company, Firstenergy Nuclear
Generation Corp., Ohio Edison
Company, the Toledo Edison
Company, Beaver Valley Power
Station, Unit Nos. 1 And 2; Exemption
1.0
Background
FirstEnergy Nuclear Operating
Company (licensee) is the holder of
PO 00000
Frm 00083
Fmt 4703
Sfmt 4703
Facility Operating License Nos. DPR–66
and NPF–73, which authorizes
operation of the Beaver Valley Power
Station, Unit Nos. 1 and 2 (BVPS–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
Beaver County, Pennsylvania.
2.0 Request/Action
Title 10 of the Code of Federal
Regulations (10 CFR), Part 73, ‘‘Physical
protection of plants and materials,’’
Section 73.55, ‘‘Requirements for
physical protection of licensed activities
in nuclear power reactors against
radiological sabotage,’’ published March
27, 2009, effective May 26, 2009, with
a full implementation date of March 31,
2010, requires licensees to protect, with
high assurance, against radiological
sabotage by designing and
implementing comprehensive site
security plans. The amendments to 10
CFR 73.55 published on March 27,
2009, establish and update generically
applicable security requirements similar
to those previously imposed by
Commission orders issued after the
terrorist attacks of September 11, 2001,
and implemented by licensees. In
addition, the amendments to 10 CFR
73.55 include additional requirements
to further enhance site security, based
upon insights gained from
implementation of the post September
11, 2001 security orders. It is from one
of these new requirements that BVPS–
1 and 2 now seeks an exemption from
the March 31, 2010 implementation
date. All other physical security
requirements established by this recent
rulemaking have already been or will be
implemented by the licensee by March
31, 2010.
By letter dated November 30, 2009, as
supplemented by letter dated December
23, 2009, the licensee requested an
exemption in accordance with 10 CFR
73.5, ‘‘Specific exemptions.’’ The
licensee’s letters contain security
information and, accordingly, those
portions are not available to the public.
The licensee has requested an
exemption from the March 31, 2010,
compliance date stating that a number
of issues will present a significant
challenge to timely completion of the
project related to a specific requirement
in 10 CFR Part 73. The request is to
extend the compliance date for one
specific requirement from the current
March 31, 2010, deadline to December
17, 2010. Being granted this exemption
for the extension would allow the
E:\FR\FM\09MRN1.SGM
09MRN1
]]>Agencies
[Federal Register Volume 75, Number 45 (Tuesday, March 9, 2010)]
[Notices]
[Pages 10835-10836]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2010-4940]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-285; NRC-2010-0087]
Omaha Public Power District, Fort Calhoun Station, Unit 1,
Environmental Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an exemption, pursuant to Title 10 of the Code of Federal
Regulations (10 CFR) Section 73.5, ``Specific exemptions,'' from the
implementation date for certain new requirements of 10 CFR part 73,
``Physical protection of plants and materials,'' for Renewed Facility
Operating License No. DPR-40, issued to Omaha Public Power District
(OPPD, the licensee), for operation of Fort Calhoun Station, Unit 1
(FCS), located in Washington County, Nebraska. 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.
Environmental Assessment
Identification of the Proposed Action
The proposed action would exempt FCS from the required
implementation date of March 31, 2010, for several new requirements of
10 CFR part 73. Specifically, FCS would be granted an exemption from
being in full compliance with certain new requirements contained in 10
CFR 73.55 by the March 31, 2010, deadline. OPPD has proposed an
alternate full compliance implementation date of October 5, 2011,
approximately 19 months beyond the date required by 10 CFR part 73. The
proposed action, an extension of the schedule for completion of certain
actions required by the revised 10 CFR part 73, does not involve any
physical changes to the reactor, fuel, plant structures, support
structures, water, or land at the FCS site.
The proposed action is in accordance with the licensee's
application dated December 31, 2009, as supplemented by letter dated
January 21, 2010.
The Need for the Proposed Action
The proposed action is needed to provide the licensee with
additional time to perform the required upgrades to the FCS security
system due to the time required for significant design, procurement,
and installation activities needed to implement the required upgrades.
Environmental Impacts of the Proposed Action
The NRC has completed its environmental assessment of the proposed
exemption. The staff has concluded that the proposed action to extend
the implementation deadline would not significantly affect plant safety
and would not have a significant adverse effect on the probability of
an accident occurring.
The proposed action would not result in an increased radiological
hazard beyond those previously analyzed in the environmental assessment
and finding of no significant impact made by the Commission in
promulgating its revisions to 10 CFR part 73 as discussed in a Federal
Register notice dated March 27, 2009 (74 FR 13926). There will be no
change to radioactive effluents that affect radiation exposures to
plant workers and members of the public. Therefore, no changes or
different types of radiological impacts are expected as a result of the
proposed exemption.
The proposed action does not result in changes to land use or water
use, or result in changes to the quality or quantity of non-
radiological effluents.
[[Page 10836]]
No changes to the National Pollution Discharge Elimination System
permit are needed. No effects on the aquatic or terrestrial habitat in
the vicinity of the plant, or to threatened, endangered, or protected
species under the Endangered Species Act, or impacts to essential fish
habitat covered by the Magnuson-Steven's Act are expected. There are no
impacts to the air or ambient air quality. There are no impacts to
historical and cultural resources. There would be no impact to
socioeconomic resources. Therefore, no changes to or different types of
non-radiological environmental impacts are expected as a result of the
proposed exemption.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action. In addition,
in promulgating its revisions to 10 CFR part 73, the Commission
prepared an environmental assessment and published a finding of no
significant impact [Part 73, Power Reactor Security Requirements, 74 FR
13926 (March 27, 2009)].
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 to the regulation, if granted.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to the proposed actions, the NRC staff considered
denial of the proposed actions (i.e., the ``no-action'' alternative).
Denial of the exemption request would result in no change in current
environmental impacts. If the proposed action was denied, the licensee
would have to comply with the March 31, 2010, implementation deadline.
The environmental impacts of the proposed exemption and the ``no-
action'' alternative are similar.
Alternative Use of Resources
The action does not involve the use of any different resources than
those considered in the Final Environmental Statement for the FCS dated
August 1972, as supplemented through the ``Generic Environmental Impact
Statement for License Renewal of Nuclear Plants: Fort Calhoun Station
Unit 1--Final Report (NUREG-1437, Supplement 12).''
Agencies and Persons Consulted
In accordance with its stated policy, on February 4, 2010, the NRC
staff consulted with the Nebraska State official, Julia Schmitt, of the
Department of Health and Human Services Regulation and Licensure,
regarding the environmental impact of the proposed action. 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 December 31, 2009, as supplemented by letter
dated January 21, 2010. The January 21, 2010, submittal and portions of
the December 31, 2009, submittal contain security-related information
and, accordingly, are exempt from public disclosure. Other parts of the
December 31, 2009, document may be examined, and/or copied for a fee,
at the NRC's Public Document Room (PDR), located at One White Flint
North, Room O-1 F21, 11555 Rockville Pike (first floor), Rockville,
Maryland 20852. 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.resource@nrc.gov.
Dated at Rockville, Maryland, this 2nd day of March 2010.
For the Nuclear Regulatory Commission.
Lynnea Wilkins,
Project Manager, Plant Licensing Branch IV, Division of Operating
Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. 2010-4940 Filed 3-8-10; 8:45 am]
BILLING CODE 7590-01-P
