LaCrosse Boiling Water Reactor, Exemption From Certain Requirements, Vernon County, WI, 27097-27099 [2012-11038]
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Federal Register / Vol. 77, No. 89 / Tuesday, May 8, 2012 / Notices
321–867–7214; Facsimile: 321–867–
1817.
FOR FURTHER INFORMATION CONTACT:
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Facsimile: 321–867–1817. Information
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[FR Doc. 2012–10955 Filed 5–7–12; 8:45 am]
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srobinson on DSK4SPTVN1PROD with NOTICES
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[FR Doc. 2012–10956 Filed 5–7–12; 8:45 am]
This notice is issued in
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Competing applications completed and
SUMMARY:
VerDate Mar<15>2010
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Jkt 226001
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Dated: Friday, May 4, 2012.
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[FR Doc. 2012–11185 Filed 5–4–12; 4:15 pm]
BILLING CODE 7533–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2012–0102; Docket No. 50–409,
License DPR–045]
LaCrosse Boiling Water Reactor,
Exemption From Certain
Requirements, Vernon County, WI
Nuclear Regulatory
Commission.
ACTION: Environmental assessment and
finding of no significant impact.
AGENCY:
John
Hickman, Division of Waste
Management and Environmental
Protection, Office of Federal and State
Materials and Environmental
Management Programs, U.S. Nuclear
Regulatory Commission, Mail Stop
T8F5, Washington, DC 20555–0001;
telephone: 301–415–3017; email:
John.Hickman@nrc.gov.
FOR FURTHER INFORMATION CONTACT:
SUPPLEMENTARY INFORMATION:
NATIONAL TRANSPORTATION
SAFETY BOARD
Sunshine Act Meeting
9:30 a.m., Tuesday, May
22, 2012.
PLACE: NTSB Conference Center, 429
L’Enfant Plaza SW., Washington, DC
20594.
STATUS: The one item is open to the
public.
MATTER TO BE CONSIDERED:
8413, Safety Study: The Safety of
Experimental Amateur-Built Aircraft.
NEWS MEDIA CONTACT: Telephone: (202)
314–6100.
The press and public may enter the
NTSB Conference Center one hour prior
to the meeting for set up and seating.
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bingc@ntsb.gov.
TIME AND DATE:
PO 00000
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Fmt 4703
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I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC or the Commission)
staff is considering a request dated
December 1, 2010, by Dairyland Power
Cooperative, (DPC, the licensee)
requesting exemptions from certain
security requirements in Title 10 of the
Code Federal Regulations (10 CFR)
73.55, for the LaCrosse Boiling Water
Reactor (LACBWR).
This Environmental Assessment (EA)
has been developed in accordance with
the requirements of 10 CFR 51.21.
II. Environmental Assessment
Identification of Proposed Action
The proposed action would exempt
LACBWR, a 10 CFR Part 50 licensee,
from certain 10 CFR Part 73 security
requirements because LACBWR is
permanently shut-down and defueled.
The part of this proposed action
involving safeguards plans meets the
categorical exclusion provision in 10
CFR 51.22(c)(25)(vi)(F), because it is an
exemption from the Commission’s
regulations and (i) there is no significant
hazards consideration; (ii) there is no
significant change in the types or
significant increase in the amounts of
any effluents that may be released
offsite; (iii) there is no significant
increase in individual or cumulative
E:\FR\FM\08MYN1.SGM
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27098
Federal Register / Vol. 77, No. 89 / Tuesday, May 8, 2012 / Notices
srobinson on DSK4SPTVN1PROD with NOTICES
public or occupational radiation
exposure; (iv) there is no significant
construction impact; (v) there is no
significant increase in the potential for
or consequences from radiological
accidents; and (vi) the requirements
from which an exemption is sought
involve safeguard plans (which include
physical protection plans). Therefore,
this part of the action does not require
either an environmental assessment or
an environmental impact statement.
This environmental assessment was
prepared for the part of the proposed
action that does not involve safeguards
plans (i.e., the exemption from the
implementation date required by 10
CFR 73.55(a)(1)).
Need for Proposed Action
The NRC revised 10 CFR 73.55
through the issuance of a final rule on
March 27, 2009 (74 FR 13926). Section
73.55 requires that licensees establish
and maintain physical protection and
security for activities involving special
nuclear material (SNM). Section
73.55(a)(1) requires implementation of
the 10 CFR 73.55 requirements by
March 31, 2010. The revised regulation
stated that it was applicable to all Part
50 licensees. The NRC became aware
that many Part 50 licensees with
facilities in decommissioning status did
not recognize the applicability of this
regulation to their facilities. By letter
dated August 2, 2010, the NRC
discussed the applicability of the
revised 10 CFR 73.55 to all Part 50
licensees, stating that each licensee
needs to evaluate the applicability of the
regulation to its facility and either make
appropriate changes to its Physical
Security Plan (PSP), or request an
exemption.
The proposed action is needed
because the permanently shut-down and
defueled status of LACBWR affects the
level of security necessary to protect
against radiological sabotage or
diversion and the implementation date
in 10 CFR 73.55(a)(1) has passed. The
shutdown status of LACBWR means that
there are no longer interconnected
operating systems which require
security to prevent offsite releases or
protect SNM. Granting the licensee an
exemption from the March 31, 2010,
implementation date would allow the
licensee to continue to follow its
existing, NRC-approved PSP.
Environmental Impacts of the Proposed
Action
The NRC staff evaluated the
environmental impacts of the proposed
action and concludes that exempting the
facility from the implementation date
will not have any adverse
VerDate Mar<15>2010
17:33 May 07, 2012
Jkt 226001
environmental impacts. The NRC staff
has also determined that the proposed
action alleviates the licensee from
complying with security requirements
that are not necessary for the
permanently shut-down and defueled
status. In addition, there will be no
construction or major renovation of any
buildings or structures, no ground
disturbing activities, no alteration to
land or air quality, or any affect on
historic and cultural resources
associated with an extension of the
compliance deadline. Therefore, the
proposed action does not reduce the
protection of the stored spent fuel. The
proposed action will not significantly
increase the probability or consequences
of accidents, no changes are being made
in the types of any effluents that may be
released offsite, and 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, there will be no
construction or renovation of buildings
or structures, or any ground disturbing
activities associated with an extension
of the compliance deadline. In addition
the proposed action does not affect nonradiological plant effluents and has no
other environmental impact. Finally,
there will be no impact on historic sites.
Therefore, there are no significant nonradiological environmental impacts
associated with the proposed action.
Accordingly, the NRC staff 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 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 because there will be no
construction or major renovation of any
buildings or structures, nor any ground
disturbing activities associated with an
extension of the compliance deadline.
Thus the environmental impacts of the
proposed action and no-action
alternative are similar. Therefore, the
no-action alternative is not further
considered.
Conclusion
The NRC staff has concluded that the
proposed action will not significantly
impact the quality of the human
environment, and that the proposed
action is the preferred alternative.
PO 00000
Frm 00086
Fmt 4703
Sfmt 4703
Agencies and Persons Consulted
In accordance with its stated policy,
on August 23, 2011, the NRC staff
consulted with the Wisconsin State
official of the Radiation Protection
Section, Wisconsin Department of
Health Services, regarding the
environmental impact of the proposed
action. The State official had no
comments.
The NRC staff has determined that the
proposed action is of a procedural
nature, and will not affect listed species
or critical habitat. Therefore, no further
consultation is required under Section 7
of the Endangered Species Act. The
NRC staff has also determined that the
proposed action is not the type of
activity that has the potential to cause
effects on historic properties. Therefore,
no further consultation is required
under Section 106 of the National
Historic Preservation Act.
III. Finding of No Significant Impact
The NRC staff has prepared this EA as
part of its review of the proposed action.
On the basis of this EA, the NRC finds
that there are no significant
environmental impacts from the
proposed action, and that preparation of
an environmental impact statement is
not warranted. Accordingly, the NRC
has determined that a Finding of No
Significant Impact is appropriate.
IV. Further Information
For further details with respect to the
proposed action, see the licensee’s letter
dated December 1, 2010, [ADAMS
Accession Number ML103400106].
Documents related to this action,
including the application and
supporting documentation, are available
online in the NRC Library at https://
www.nrc.gov/reading-rm/adams.html.
From this site, you can access the NRC’s
Agencywide Document Access and
Management System (ADAMS), which
provides text and image files of NRC’s
public documents.
If you do not have access to ADAMS,
or if there are problems in accessing the
documents located in ADAMS, contact
the NRC Public Document Room (PDR)
Reference staff at 1–800–397–4209, 301–
415–4737, or by email to
pdr.resource@nrc.gov. These documents
may also be viewed electronically on
the public computers located at the
NRC’s PDR, O 1 F21, One White Flint
North, 11555 Rockville Pike, Rockville,
MD 20852. The PDR reproduction
contractor will copy documents for a
fee.
Dated at Rockville, Maryland, this 30th day
of April 2012.
E:\FR\FM\08MYN1.SGM
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Federal Register / Vol. 77, No. 89 / Tuesday, May 8, 2012 / Notices
For the Nuclear Regulatory Commission.
Bruce Watson,
Acting Deputy Director, Decommissioning
and Uranium Recovery Licensing Directorate,
Division of Waste Management and
Environmental Protection, Office of Federal
and State Materials and Environmental
Management Programs.
[FR Doc. 2012–11038 Filed 5–7–12; 8:45 am]
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NUCLEAR REGULATORY
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Frm 00087
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27099
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]]>Agencies
[Federal Register Volume 77, Number 89 (Tuesday, May 8, 2012)]
[Notices]
[Pages 27097-27099]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-11038]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2012-0102; Docket No. 50-409, License DPR-045]
LaCrosse Boiling Water Reactor, Exemption From Certain
Requirements, Vernon County, WI
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: John Hickman, Division of Waste
Management and Environmental Protection, Office of Federal and State
Materials and Environmental Management Programs, U.S. Nuclear
Regulatory Commission, Mail Stop T8F5, Washington, DC 20555-0001;
telephone: 301-415-3017; email: John.Hickman@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC or the Commission)
staff is considering a request dated December 1, 2010, by Dairyland
Power Cooperative, (DPC, the licensee) requesting exemptions from
certain security requirements in Title 10 of the Code Federal
Regulations (10 CFR) 73.55, for the LaCrosse Boiling Water Reactor
(LACBWR).
This Environmental Assessment (EA) has been developed in accordance
with the requirements of 10 CFR 51.21.
II. Environmental Assessment
Identification of Proposed Action
The proposed action would exempt LACBWR, a 10 CFR Part 50 licensee,
from certain 10 CFR Part 73 security requirements because LACBWR is
permanently shut-down and defueled. The part of this proposed action
involving safeguards plans meets the categorical exclusion provision in
10 CFR 51.22(c)(25)(vi)(F), because it is an exemption from the
Commission's regulations and (i) there is no significant hazards
consideration; (ii) there is no significant change in the types or
significant increase in the amounts of any effluents that may be
released offsite; (iii) there is no significant increase in individual
or cumulative
[[Page 27098]]
public or occupational radiation exposure; (iv) there is no significant
construction impact; (v) there is no significant increase in the
potential for or consequences from radiological accidents; and (vi) the
requirements from which an exemption is sought involve safeguard plans
(which include physical protection plans). Therefore, this part of the
action does not require either an environmental assessment or an
environmental impact statement. This environmental assessment was
prepared for the part of the proposed action that does not involve
safeguards plans (i.e., the exemption from the implementation date
required by 10 CFR 73.55(a)(1)).
Need for Proposed Action
The NRC revised 10 CFR 73.55 through the issuance of a final rule
on March 27, 2009 (74 FR 13926). Section 73.55 requires that licensees
establish and maintain physical protection and security for activities
involving special nuclear material (SNM). Section 73.55(a)(1) requires
implementation of the 10 CFR 73.55 requirements by March 31, 2010. The
revised regulation stated that it was applicable to all Part 50
licensees. The NRC became aware that many Part 50 licensees with
facilities in decommissioning status did not recognize the
applicability of this regulation to their facilities. By letter dated
August 2, 2010, the NRC discussed the applicability of the revised 10
CFR 73.55 to all Part 50 licensees, stating that each licensee needs to
evaluate the applicability of the regulation to its facility and either
make appropriate changes to its Physical Security Plan (PSP), or
request an exemption.
The proposed action is needed because the permanently shut-down and
defueled status of LACBWR affects the level of security necessary to
protect against radiological sabotage or diversion and the
implementation date in 10 CFR 73.55(a)(1) has passed. The shutdown
status of LACBWR means that there are no longer interconnected
operating systems which require security to prevent offsite releases or
protect SNM. Granting the licensee an exemption from the March 31,
2010, implementation date would allow the licensee to continue to
follow its existing, NRC-approved PSP.
Environmental Impacts of the Proposed Action
The NRC staff evaluated the environmental impacts of the proposed
action and concludes that exempting the facility from the
implementation date will not have any adverse environmental impacts.
The NRC staff has also determined that the proposed action alleviates
the licensee from complying with security requirements that are not
necessary for the permanently shut-down and defueled status. In
addition, there will be no construction or major renovation of any
buildings or structures, no ground disturbing activities, no alteration
to land or air quality, or any affect on historic and cultural
resources associated with an extension of the compliance deadline.
Therefore, the proposed action does not reduce the protection of the
stored spent fuel. The proposed action will not significantly increase
the probability or consequences of accidents, no changes are being made
in the types of any effluents that may be released offsite, and 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 non-radiological impacts, there will be no
construction or renovation of buildings or structures, or any ground
disturbing activities associated with an extension of the compliance
deadline. In addition the proposed action does not affect non-
radiological plant effluents and has no other environmental impact.
Finally, there will be no impact on historic sites. Therefore, there
are no significant non-radiological environmental impacts associated
with the proposed action.
Accordingly, the NRC staff 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 NRC staff considered
denial of the proposed action (i.e., the ``no-action'' alternative).
Denial of the exemption request would result in no change in current
environmental impacts because there will be no construction or major
renovation of any buildings or structures, nor any ground disturbing
activities associated with an extension of the compliance deadline.
Thus the environmental impacts of the proposed action and no-action
alternative are similar. Therefore, the no-action alternative is not
further considered.
Conclusion
The NRC staff has concluded that the proposed action will not
significantly impact the quality of the human environment, and that the
proposed action is the preferred alternative.
Agencies and Persons Consulted
In accordance with its stated policy, on August 23, 2011, the NRC
staff consulted with the Wisconsin State official of the Radiation
Protection Section, Wisconsin Department of Health Services, regarding
the environmental impact of the proposed action. The State official had
no comments.
The NRC staff has determined that the proposed action is of a
procedural nature, and will not affect listed species or critical
habitat. Therefore, no further consultation is required under Section 7
of the Endangered Species Act. The NRC staff has also determined that
the proposed action is not the type of activity that has the potential
to cause effects on historic properties. Therefore, no further
consultation is required under Section 106 of the National Historic
Preservation Act.
III. Finding of No Significant Impact
The NRC staff has prepared this EA as part of its review of the
proposed action. On the basis of this EA, the NRC finds that there are
no significant environmental impacts from the proposed action, and that
preparation of an environmental impact statement is not warranted.
Accordingly, the NRC has determined that a Finding of No Significant
Impact is appropriate.
IV. Further Information
For further details with respect to the proposed action, see the
licensee's letter dated December 1, 2010, [ADAMS Accession Number
ML103400106]. Documents related to this action, including the
application and supporting documentation, are available online in the
NRC Library at https://www.nrc.gov/reading-rm/adams.html. From this
site, you can access the NRC's Agencywide Document Access and
Management System (ADAMS), which provides text and image files of NRC's
public documents.
If you do not have access to ADAMS, or if there are problems in
accessing the documents located in ADAMS, contact the NRC Public
Document Room (PDR) Reference staff at 1-800-397-4209, 301-415-4737, or
by email to pdr.resource@nrc.gov. These documents may also be viewed
electronically on the public computers located at the NRC's PDR, O 1
F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852.
The PDR reproduction contractor will copy documents for a fee.
Dated at Rockville, Maryland, this 30th day of April 2012.
[[Page 27099]]
For the Nuclear Regulatory Commission.
Bruce Watson,
Acting Deputy Director, Decommissioning and Uranium Recovery Licensing
Directorate, Division of Waste Management and Environmental Protection,
Office of Federal and State Materials and Environmental Management
Programs.
[FR Doc. 2012-11038 Filed 5-7-12; 8:45 am]
BILLING CODE 7590-01-P
