Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Materials License No. 47-00260-02, for Termination of the License and Unrestricted Release of Two Union Carbide Corporation Facilities Located in South Charleston, WV, 29730-29732 [E9-14684]
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Federal Register / Vol. 74, No. 119 / Tuesday, June 23, 2009 / Notices
Declassification Act of 2000 (Pub. L.
106–567, title VII, December 27, 2000,
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for the following committee meeting:
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Dated: June 11, 2009.
Mary Ann Hadyka,
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[FR Doc. E9–14691 Filed 6–22–09; 8:45 am]
BILLING CODE 7515–01–P
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Programs and Plans; Sunshine Act
Meetings; Notice
The National Science Board’s
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pursuant to NSF regulations (45 CFR
Part 614), the National Science
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[FR Doc. E9–14914 Filed 6–19–09; 4:15 pm]
BILLING CODE 7555–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2009–0255; Docket No. 030–06652]
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment to Byproduct Materials
License No. 47–00260–02, for
Termination of the License and
Unrestricted Release of Two Union
Carbide Corporation Facilities Located
in South Charleston, WV
AGENCY: Nuclear Regulatory
Commission.
ACTION: Issuance of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment.
FOR FURTHER INFORMATION CONTACT:
Steve Hammann, Health Physicist,
Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I,
475 Allendale Road, King of Prussia,
Pennsylvania; telephone 610–337–5399;
fax number 610–337–5269; or by e-mail:
stephen.hammann@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is considering the
issuance of a license amendment to
Byproduct Materials License No. 47–
00260–02. This license is held by Union
Carbide Corporation (the Licensee) for
its South Charleston Technology Park
and South Charleston Plant located,
respectively, at 3200 Kanawha Turnpike
in South Charleston, West Virginia, and
at 437 MacCorkle Avenue in South
Charleston, West Virginia (the
PO 00000
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Fmt 4703
Sfmt 4703
Facilities). Issuance of the amendment
would authorize release of the Facilities
for unrestricted use and termination of
the NRC license. The Licensee requested
this action in a letter dated March 7,
2008. The NRC has prepared an
Environmental Assessment (EA) in
support of this proposed action in
accordance with the requirements of
Title 10, Code of Federal Regulations
(CFR), part 51 (10 CFR part 51). Based
on the EA, the NRC has concluded that
a Finding of No Significant Impact
(FONSI) is appropriate with respect to
the proposed action. The amendment
will be issued to the Licensee following
the publication of this FONSI and EA in
the Federal Register.
II. Environmental Assessment
Identification of Proposed Action
The proposed action would approve
the Licensee’s March 7, 2008, license
amendment request, resulting in release
of the Facilities for unrestricted use and
the termination of its NRC materials
license. License No. 47–00260–02 was
issued on August 15, 1956, pursuant to
10 CFR part 30, and has been amended
periodically since that time. This
license authorized the Licensee to use
sealed and unsealed byproduct material
for purposes of conducting research and
development activities, sample analysis
and instrument calibration.
The Facilities are situated on
approximately 850 acres of land and
consists of undeveloped land and
numerous buildings used for a variety of
purposes, including office space and
laboratories, storage, and
manufacturing. The Facilities are
located in a mixed commercial and
industrial area. Within the Facilities,
use of licensed materials was confined
to Buildings 701, 707, 712, 720, 722,
725, 727, 740, 741, 747, 770, 771, 773,
776, 777, 778, and 785.
In April, 2008, the Licensee ceased
licensed activities and initiated a survey
and decontamination of the Facilities.
Based on the Licensee’s historical
knowledge of the sites and the condition
of the Facilities, the Licensee
determined that only routine
decontamination activities, in
accordance with their NRC-approved,
operating radiation safety procedures,
were required. The Licensee was not
required to submit a decommissioning
plan to the NRC because worker cleanup
activities and procedures are consistent
with those approved for routine
operations. The Licensee conducted
surveys of the Facilities and provided
information to the NRC to demonstrate
that it meets the criteria in subpart E of
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Federal Register / Vol. 74, No. 119 / Tuesday, June 23, 2009 / Notices
10 CFR part 20 for unrestricted release
and for license termination.
Need for the Proposed Action
The Licensee has ceased conducting
licensed activities at the Facilities, and
seeks the unrestricted use of its
Facilities and the termination of its NRC
materials license. Termination of its
license would end the Licensee’s
obligation to pay annual license fees to
the NRC.
Environmental Impacts of the Proposed
Action
The historical review of licensed
activities conducted at the Facilities
show that such activities involved use
of the following radionuclides with halflives greater than 120 days: hydrogen-3,
carbon-14, iron-55, cobalt-60, nickel-63,
strontium-90, cadmium-109, cesium137, and polonium-210. Prior to
performing the final status survey, the
Licensee conducted decontamination
activities, as necessary, in the areas of
the Facilities affected by these
radionuclides.
The Licensee finished conducting a
final status survey on November 17,
2008. This survey covered all buildings
which used unsealed materials. The
final status survey report was attached
to the Licensee’s amendment request
dated March 7, 2008. The Licensee
elected to demonstrate compliance with
the radiological criteria for unrestricted
release as specified in 10 CFR 20.1402
by using the screening approach
described in NUREG–1757,
‘‘Consolidated NMSS Decommissioning
Guidance,’’ Volume 2. The Licensee
used the radionuclide-specific derived
concentration guideline levels (DCGLs),
developed there by the NRC, which
comply with the dose criteria in 10 CFR
20.1402. These DCGLs define the
maximum amount of residual
radioactivity on building surfaces,
equipment, and materials, and in soils
that will satisfy the NRC requirements
in subpart E of 10 CFR part 20 for
unrestricted release. The Licensee’s
final status survey results were below
these DCGLs and are in compliance
with the As Low As Reasonably
Achievable (ALARA) requirement of 10
CFR 20.1402. The NRC thus finds that
the Licensee’s final status survey results
are acceptable.
Based on its review, the staff has
determined that the affected
environment and any environmental
impacts associated with the proposed
action are bounded by the impacts
evaluated by the ‘‘Generic
Environmental Impact Statement in
Support of Rulemaking on Radiological
Criteria for License Termination of NRC-
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Licensed Nuclear Facilities’’ (NUREG–
1496) Volumes 1–3 (ML042310492,
ML042320379, and ML042330385). The
staff finds there were no significant
environmental impacts from the use of
radioactive material at the Facilities.
The NRC staff reviewed the docket file
records and the final status survey
report to identify any non-radiological
hazards that may have impacted the
environment surrounding the Facilities.
No such hazards or impacts to the
environment were identified. The NRC
has identified no other radiological or
non-radiological activities in the area
that could result in cumulative
environmental impacts.
The NRC staff finds that the proposed
release of the Facilities for unrestricted
use and the termination of the NRC
materials license is in compliance with
10 CFR 20. Based on its review, the staff
considered the impact of the residual
radioactivity at the Facilities and
concluded that the proposed action will
not have a significant effect on the
quality of the human environment.
Environmental Impacts of the
Alternatives to the Proposed Action
Due to the largely administrative
nature of the proposed action, its
environmental impacts are small.
Therefore, the only alternative the staff
considered is the no-action alternative,
under which the staff would leave
things as they are by simply denying the
amendment request. This no-action
alternative is not feasible because it
conflicts with 10 CFR 30.36(d),
requiring that decommissioning of
byproduct material facilities be
completed and approved by the NRC
after licensed activities cease. The
NRC’s analysis of the Licensee’s final
status survey data confirmed that the
Facilities meets the requirements of 10
CFR 20.1402 for unrestricted release and
for license termination. Additionally,
denying the amendment request would
result in no change in current
environmental impacts. The
environmental impacts of the proposed
action and the no-action alternative are
therefore similar, and the no-action
alternative is accordingly not further
considered.
Conclusion
The NRC staff has concluded that the
proposed action is consistent with the
NRC’s unrestricted release criteria
specified in 10 CFR 20.1402. Because
the proposed action will not
significantly impact the quality of the
human environment, the NRC staff
concludes that the proposed action is
the preferred alternative.
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Fmt 4703
Sfmt 4703
29731
Agencies and Persons Consulted
NRC provided a draft of this
Environmental Assessment to the State
of West Virginia Office of
Environmental Health Services for
review on April 9, 2009. On June 4,
2009, the State responded by telephone.
The State agreed with the conclusions of
the EA, and otherwise 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 in
support 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
Documents related to this action,
including the application for license
amendment and supporting
documentation, are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this site,
you can access the NRC’s Agencywide
Documents Access and Management
System (ADAMS), which provides text
and image files of NRC’s public
documents. The documents related to
this action are listed below, along with
their ADAMS accession numbers.
1. NUREG–1757, ‘‘Consolidated
NMSS Decommissioning Guidance’’;
2. Title 10 Code of Federal
Regulations, Part 20, Subpart E,
‘‘Radiological Criteria for License
Termination’’;
3. Title 10, Code of Federal
Regulations, Part 51, ‘‘Environmental
Protection Regulations for Domestic
Licensing and Related Regulatory
Functions’’;
4. NUREG–1496, ‘‘Generic
Environmental Impact Statement in
Support of Rulemaking on Radiological
Criteria for License Termination of NRCLicensed Nuclear Facilities’’;
5. Termination Request Letter dated
March 7, 2008 (ML083520561);
E:\FR\FM\23JNN1.SGM
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Federal Register / Vol. 74, No. 119 / Tuesday, June 23, 2009 / Notices
6. Request For Additional Information
dated April 30, 2008 (ML081260393);
and
7. Deficiency Response Letter dated
December 11, 2008 (ML083520561).
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 e-mail to pdr@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 Region I, 475 Allendale Road,
King of Prussia, Pennsylvania this 15th day
of June 2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I.
[FR Doc. E9–14684 Filed 6–22–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–302; NRC–2009–0256]
Crystal River Unit 3; Notice of
Consideration of Issuance of
Amendment to Facility Operating
License, Proposed No Significant
Hazards Consideration Determination,
and Opportunity for a Hearing
The U.S. Nuclear Regulatory
Commission (the Commission) is
considering issuance of an amendment
to Facility Operating License No. DPR–
72 issued to Florida Power Corporation,
et al (the licensee) for operation of the
Crystal River Unit No. 3 Nuclear
Generating Plant, located in Citrus
County, Florida.
The proposed amendment would
revise the Crystal River Unit 3 (CR–3)
Final Safety Analysis Report (FSAR)
Sections 5.4.3, ‘‘Structural Design
Criteria’’ and 5.4.5.3, ‘‘Missile
Analysis,’’ to include a statement
regarding the design of the east wall of
the CR–3 Auxiliary Building. The
amendment would change the
methodology used to qualify the east
wall of the Auxiliary Building. The
current methodology used the methods
in American Concrete Institute (ACI)
standard 318–63, ‘‘Building Code
Requirements for Reinforced Concrete,’’
June 1963. The proposed methodology
is based on ACI 349–97, ‘‘Code
Requirements for Nuclear Safety Related
Concrete Structures,’’ as endorsed by
VerDate Nov<24>2008
16:15 Jun 22, 2009
Jkt 217001
the Standard Review Plan (NUREG
0800), Revision 2—March 2007, Section
3.8.4 ‘‘Other Seismic Category 1
Structures.’’
Before issuance of the proposed
license amendment, the Commission
will have made findings required by the
Atomic Energy Act of 1954, as amended
(the Act), and the Commission’s
regulations.
The Commission has made a
proposed determination that the
amendment request involves no
significant hazards consideration. Under
the Commission’s regulations in Title 10
of the Code of Federal Regulations (10
CFR), Section 50.92, this means that
operation of the facility in accordance
with the proposed amendment would
not (1) involve a significant increase in
the probability or consequences of an
accident previously evaluated; or (2)
create the possibility of a new or
different kind of accident from any
accident previously evaluated; or (3)
involve a significant reduction in a
margin of safety. As required by 10 CFR
50.91(a), the licensee has provided its
analysis of the issue of no significant
hazards consideration, which is
presented below:
1. Does not involve a significant increase
in the probability or consequences of an
accident previously evaluated.
The proposed LAR will revise the
methodology used to qualify the east wall of
the CR–3 Auxiliary Building for all expected
and postulated loads including tornado wind
and missile loading. The Yield Line Theory
methodology is an industry standard that is
used for the design and analysis of concrete
slabs and is applied to CR–3 in accordance
with American Concrete Institute (ACI) 349–
97, ‘‘Code Requirements for Nuclear Safety
Related Concrete Structures.’’ A change in
the methodology of an analysis used to verify
qualification of an existing structure will not
have any impact on the probability of
accidents previously evaluated.
The analysis performed demonstrates that
the CR–3 Auxiliary Building east wall will
remain structurally intact following the worst
case loadings assumed in the calculation.
Therefore, this proposed change does not
involve a significant increase in the
probability or consequences previously
evaluated.
2. Does not create the possibility of a new
or different kind of accident from any
accident previously evaluated.
The function of the CR–3 Auxiliary
Building wall is to house and protect the
equipment that is important to safety from
damage during normal operation, transients,
and design basis accidents. The use of ACI
349–97 for qualifying the east wall of the CR–
3 Auxiliary Building has no impact on the
capability of the structure. A calculation that
uses the Yield Line Theory methodology
demonstrated that the structure meets
required design criteria. This ensures that the
wall is capable of performing its design basis
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Fmt 4703
Sfmt 4703
function without alteration or compensatory
actions of any kind. No changes to any plant
system, structure, or component (SSC) are
proposed. No changes to any plant operating
practices, procedures, computer firmware/
software will occur.
Therefore, the proposed change will not
create the possibility of new or different type
of accident from any previously evaluated.
3. Does not involve a significant reduction
in a margin on safety.
The design basis of the plant requires
structures to be capable of withstanding
normal and accident loads including those
from a design basis tornado. The
requirements of ACI 349–97, as applied in an
approved plant calculation, demonstrated
that the east wall of the CR–3 Auxiliary
Building is capable of performing its design
function. There is a slight reduction in
conservatism between the method used for
the remaining Class 1 structures, ACI 318–63
and ACI 349–97, but the calculation
performed validates the requirement that the
east wall of the Auxiliary Building will
protect the important to safety systems,
structures, and components located in
proximity to the wall from damage.
Therefore, the proposed change does not
involve a significant reduction in the margin
of safety.
The NRC staff has reviewed the
licensee’s analysis and, based on this
review, it appears that the three
standards of 10 CFR 50.92(c) are
satisfied. Therefore, the NRC staff
proposes to determine that the
amendment request involves no
significant hazards consideration.
The Commission is seeking public
comments on this proposed
determination. Any comments received
within 30 days after the date of
publication of this notice will be
considered in making any final
determination.
Normally, the Commission will not
issue the amendment until the
expiration of 60 days after the date of
publication of this notice. The
Commission may issue the license
amendment before expiration of the 60day period provided that its final
determination is that the amendment
involves no significant hazards
consideration. In addition, the
Commission may issue the amendment
prior to the expiration of the 30-day
comment period should circumstances
change during the 30-day comment
period such that failure to act in a
timely way would result, for example,
in derating or shutdown of the facility.
Should the Commission take action
prior to the expiration of either the
comment period or the notice period, it
will publish in the Federal Register a
notice of issuance. Should the
Commission make a final No Significant
Hazards Consideration Determination,
any hearing will take place after
E:\FR\FM\23JNN1.SGM
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]]>Agencies
[Federal Register Volume 74, Number 119 (Tuesday, June 23, 2009)]
[Notices]
[Pages 29730-29732]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-14684]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2009-0255; Docket No. 030-06652]
Notice of Availability of Environmental Assessment and Finding of
No Significant Impact for License Amendment to Byproduct Materials
License No. 47-00260-02, for Termination of the License and
Unrestricted Release of Two Union Carbide Corporation Facilities
Located in South Charleston, WV
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of Environmental Assessment and Finding of No
Significant Impact for License Amendment.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Steve Hammann, Health Physicist,
Commercial and R&D Branch, Division of Nuclear Materials Safety, Region
I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610-
337-5399; fax number 610-337-5269; or by e-mail:
stephen.hammann@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) is considering the
issuance of a license amendment to Byproduct Materials License No. 47-
00260-02. This license is held by Union Carbide Corporation (the
Licensee) for its South Charleston Technology Park and South Charleston
Plant located, respectively, at 3200 Kanawha Turnpike in South
Charleston, West Virginia, and at 437 MacCorkle Avenue in South
Charleston, West Virginia (the Facilities). Issuance of the amendment
would authorize release of the Facilities for unrestricted use and
termination of the NRC license. The Licensee requested this action in a
letter dated March 7, 2008. The NRC has prepared an Environmental
Assessment (EA) in support of this proposed action in accordance with
the requirements of Title 10, Code of Federal Regulations (CFR), part
51 (10 CFR part 51). Based on the EA, the NRC has concluded that a
Finding of No Significant Impact (FONSI) is appropriate with respect to
the proposed action. The amendment will be issued to the Licensee
following the publication of this FONSI and EA in the Federal Register.
II. Environmental Assessment
Identification of Proposed Action
The proposed action would approve the Licensee's March 7, 2008,
license amendment request, resulting in release of the Facilities for
unrestricted use and the termination of its NRC materials license.
License No. 47-00260-02 was issued on August 15, 1956, pursuant to 10
CFR part 30, and has been amended periodically since that time. This
license authorized the Licensee to use sealed and unsealed byproduct
material for purposes of conducting research and development
activities, sample analysis and instrument calibration.
The Facilities are situated on approximately 850 acres of land and
consists of undeveloped land and numerous buildings used for a variety
of purposes, including office space and laboratories, storage, and
manufacturing. The Facilities are located in a mixed commercial and
industrial area. Within the Facilities, use of licensed materials was
confined to Buildings 701, 707, 712, 720, 722, 725, 727, 740, 741, 747,
770, 771, 773, 776, 777, 778, and 785.
In April, 2008, the Licensee ceased licensed activities and
initiated a survey and decontamination of the Facilities. Based on the
Licensee's historical knowledge of the sites and the condition of the
Facilities, the Licensee determined that only routine decontamination
activities, in accordance with their NRC-approved, operating radiation
safety procedures, were required. The Licensee was not required to
submit a decommissioning plan to the NRC because worker cleanup
activities and procedures are consistent with those approved for
routine operations. The Licensee conducted surveys of the Facilities
and provided information to the NRC to demonstrate that it meets the
criteria in subpart E of
[[Page 29731]]
10 CFR part 20 for unrestricted release and for license termination.
Need for the Proposed Action
The Licensee has ceased conducting licensed activities at the
Facilities, and seeks the unrestricted use of its Facilities and the
termination of its NRC materials license. Termination of its license
would end the Licensee's obligation to pay annual license fees to the
NRC.
Environmental Impacts of the Proposed Action
The historical review of licensed activities conducted at the
Facilities show that such activities involved use of the following
radionuclides with half-lives greater than 120 days: hydrogen-3,
carbon-14, iron-55, cobalt-60, nickel-63, strontium-90, cadmium-109,
cesium-137, and polonium-210. Prior to performing the final status
survey, the Licensee conducted decontamination activities, as
necessary, in the areas of the Facilities affected by these
radionuclides.
The Licensee finished conducting a final status survey on November
17, 2008. This survey covered all buildings which used unsealed
materials. The final status survey report was attached to the
Licensee's amendment request dated March 7, 2008. The Licensee elected
to demonstrate compliance with the radiological criteria for
unrestricted release as specified in 10 CFR 20.1402 by using the
screening approach described in NUREG-1757, ``Consolidated NMSS
Decommissioning Guidance,'' Volume 2. The Licensee used the
radionuclide-specific derived concentration guideline levels (DCGLs),
developed there by the NRC, which comply with the dose criteria in 10
CFR 20.1402. These DCGLs define the maximum amount of residual
radioactivity on building surfaces, equipment, and materials, and in
soils that will satisfy the NRC requirements in subpart E of 10 CFR
part 20 for unrestricted release. The Licensee's final status survey
results were below these DCGLs and are in compliance with the As Low As
Reasonably Achievable (ALARA) requirement of 10 CFR 20.1402. The NRC
thus finds that the Licensee's final status survey results are
acceptable.
Based on its review, the staff has determined that the affected
environment and any environmental impacts associated with the proposed
action are bounded by the impacts evaluated by the ``Generic
Environmental Impact Statement in Support of Rulemaking on Radiological
Criteria for License Termination of NRC-Licensed Nuclear Facilities''
(NUREG-1496) Volumes 1-3 (ML042310492, ML042320379, and ML042330385).
The staff finds there were no significant environmental impacts from
the use of radioactive material at the Facilities. The NRC staff
reviewed the docket file records and the final status survey report to
identify any non-radiological hazards that may have impacted the
environment surrounding the Facilities. No such hazards or impacts to
the environment were identified. The NRC has identified no other
radiological or non-radiological activities in the area that could
result in cumulative environmental impacts.
The NRC staff finds that the proposed release of the Facilities for
unrestricted use and the termination of the NRC materials license is in
compliance with 10 CFR 20. Based on its review, the staff considered
the impact of the residual radioactivity at the Facilities and
concluded that the proposed action will not have a significant effect
on the quality of the human environment.
Environmental Impacts of the Alternatives to the Proposed Action
Due to the largely administrative nature of the proposed action,
its environmental impacts are small. Therefore, the only alternative
the staff considered is the no-action alternative, under which the
staff would leave things as they are by simply denying the amendment
request. This no-action alternative is not feasible because it
conflicts with 10 CFR 30.36(d), requiring that decommissioning of
byproduct material facilities be completed and approved by the NRC
after licensed activities cease. The NRC's analysis of the Licensee's
final status survey data confirmed that the Facilities meets the
requirements of 10 CFR 20.1402 for unrestricted release and for license
termination. Additionally, denying the amendment request would result
in no change in current environmental impacts. The environmental
impacts of the proposed action and the no-action alternative are
therefore similar, and the no-action alternative is accordingly not
further considered.
Conclusion
The NRC staff has concluded that the proposed action is consistent
with the NRC's unrestricted release criteria specified in 10 CFR
20.1402. Because the proposed action will not significantly impact the
quality of the human environment, the NRC staff concludes that the
proposed action is the preferred alternative.
Agencies and Persons Consulted
NRC provided a draft of this Environmental Assessment to the State
of West Virginia Office of Environmental Health Services for review on
April 9, 2009. On June 4, 2009, the State responded by telephone. The
State agreed with the conclusions of the EA, and otherwise 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 in support 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
Documents related to this action, including the application for
license amendment and supporting documentation, are available
electronically at the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this site, you can access the
NRC's Agencywide Documents Access and Management System (ADAMS), which
provides text and image files of NRC's public documents. The documents
related to this action are listed below, along with their ADAMS
accession numbers.
1. NUREG-1757, ``Consolidated NMSS Decommissioning Guidance'';
2. Title 10 Code of Federal Regulations, Part 20, Subpart E,
``Radiological Criteria for License Termination'';
3. Title 10, Code of Federal Regulations, Part 51, ``Environmental
Protection Regulations for Domestic Licensing and Related Regulatory
Functions'';
4. NUREG-1496, ``Generic Environmental Impact Statement in Support
of Rulemaking on Radiological Criteria for License Termination of NRC-
Licensed Nuclear Facilities'';
5. Termination Request Letter dated March 7, 2008 (ML083520561);
[[Page 29732]]
6. Request For Additional Information dated April 30, 2008
(ML081260393); and
7. Deficiency Response Letter dated December 11, 2008
(ML083520561).
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 e-mail to pdr@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 Region I, 475 Allendale Road, King of Prussia,
Pennsylvania this 15th day of June 2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety,
Region I.
[FR Doc. E9-14684 Filed 6-22-09; 8:45 am]
BILLING CODE 7590-01-P
