Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Nuclear Materials License No. 29-30119-01, for Termination of the License and Unrestricted Release of the Medarex, Incorporated's Facility in Bloomsbury, NJ, 14594-14596 [E9-7153]
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14594
Federal Register / Vol. 74, No. 60 / Tuesday, March 31, 2009 / Notices
All workers of Teck-Washington, Inc.,
Pend Oreille Mine, A Subsidiary of TeckAmerican, Inc., Metaline Falls, Washington,
who became totally or partially separated
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are eligible to apply for adjustment assistance
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trade adjustment assistance under Section
246 of the Trade Act of 1974.
Signed in Washington, DC, this 13th day of
March 2009.
Linda G. Poole,
Certifying Officer, Division of Trade
Adjustment Assistance.
[FR Doc. E9–7102 Filed 3–30–09; 8:45 am]
Signed in Washington, DC, this 13th day of
March, 2009.
Elliott S. Kushner,
Certifying Officer, Division of Trade
Adjustment Assistance.
[FR Doc. E9–7100 Filed 3–30–09; 8:45 am]
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[FR Doc. E9–7091 Filed 3–30–09; 8:45 am]
BILLING CODE 7555–01–P
tjames on PRODPC61 with NOTICES
Jkt 217001
PO 00000
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment to Byproduct Nuclear
Materials License No. 29–30119–01, for
Termination of the License and
Unrestricted Release of the Medarex,
Incorporated’s Facility in Bloomsbury,
NJ
AGENCY: Nuclear Regulatory
Commission.
ACTION: Issuance of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment.
FOR FURTHER INFORMATION CONTACT:
Dennis Lawyer, Health Physicist,
Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I,
475 Allendale Road, King of Prussia,
Pennsylvania; telephone 610–337–5366;
fax number 610–337–5269; or by e-mail:
dennis.lawyer@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. 29–
30119–01. This license is held by
Medarex, Incorporated (the Licensee),
for its facilities located at 519 Route 173
West, Bloomsbury, New Jersey (the
Facility). Issuance of the amendment
would authorize release of the Facility
for unrestricted use and termination of
the NRC license. The Licensee requested
this action in a letter dated December 1,
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.
Identification of Proposed Action
The proposed action would approve
the Licensee’s December 1, 2008, license
amendment request, resulting in release
of the Facility for unrestricted use and
the termination of its NRC materials
license. License No. 29–30119–01 was
issued on February 28, 1994, pursuant
After careful review of the
application, I conclude that the claim is
of sufficient weight to justify
reconsideration of the Department of
Labor’s prior decision. The application
is, therefore, granted.
14:35 Mar 30, 2009
[Docket No. 030–33421; NRC–2009–0143]
II. Environmental Assessment
Conclusion
VerDate Nov<24>2008
NUCLEAR REGULATORY
COMMISSION
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Federal Register / Vol. 74, No. 60 / Tuesday, March 31, 2009 / Notices
to 10 CFR Part 30, and has been
amended periodically since that time.
This license authorized the Licensee to
use unsealed byproduct material for
purposes of conducting research and
development activities on laboratory
bench tops and in hoods.
The Facility is situated within a
164,130 square foot building, and
consists of general office space and
laboratories. The Facility is located in a
mixed rural/residential area. Within the
Facility, use of licensed materials with
a half-life of greater than 120 days was
confined to Room 115A. The area of
Room 115A totaled 229 square feet.
In March 2006, the Licensee ceased
licensed activities and initiated a survey
and decontamination of the Facility.
Based on the Licensee’s historical
knowledge of the site and the conditions
of the Facility, the Licensee determined
that only routine decontamination
activities, in accordance with their NRCapproved, 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
Facility and provided information to the
NRC to demonstrate that it meets the
criteria in Subpart E of 10 CFR Part 20
for unrestricted release and for license
termination.
tjames on PRODPC61 with NOTICES
Need for the Proposed Action
The Licensee has ceased conducting
licensed activities at the Facility, and
seeks the unrestricted use of its Facility
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 Facility
shows that such activities involved use
of the following radionuclides with halflives greater than 120 days: Hydrogen 3.
Prior to performing the final status
survey, the Licensee conducted
decontamination activities, as
necessary, in the areas of the Facility
affected by this radionuclide.
The Licensee conducted a final status
survey in November 2008. This survey
covered Room 115A. The final status
survey report was attached to the
Licensee’s amendment request dated
December 1, 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
VerDate Nov<24>2008
14:35 Mar 30, 2009
Jkt 217001
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 criterion in 10
CFR 20.1402. These DCGLs define the
maximum amount of residual
radioactivity on building surfaces,
equipment, and materials 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 Facility. 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 Facility. 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 Facility for unrestricted
use and the termination of the NRC
materials license is in compliance with
10 CFR 20.1402. Based on its review,
the staff considered the impact of the
residual radioactivity at the Facility 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),
PO 00000
Frm 00084
Fmt 4703
Sfmt 4703
14595
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
Facility 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 New
Jersey Department of Environmental
Protection for review on January 28,
2009. On February 26, 2009, the New
Jersey Department of Environmental
Protection responded by letter. The
State agreed with the conclusions of the
EA but noted there was use of
radioactive material in an additional
area, specifically Room 145A. NRC
noted that while the Licensee included
Room 145A in its final status survey, the
half-life of radioactive materials used in
Room 145A did not exceed 120 days.
Therefore, in accordance with the
categorical exclusion described in 10
CFR 51.22(c)(20), no environmental
assessment is required for Room 145A.
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
E:\FR\FM\31MRN1.SGM
31MRN1
14596
Federal Register / Vol. 74, No. 60 / Tuesday, March 31, 2009 / Notices
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
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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
Document 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;’’ and
5. Medarex, Incorporated termination
request letter dated December 1, 2008
(ML083510774).
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.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 Region I, 475 Allendale Road,
King of Prussia, PA this 24th day of March.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I.
[FR Doc. E9–7153 Filed 3–30–09; 8:45 am]
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Advisory Committee on Reactor
Safeguards; Subcommittee Meeting on
Safety Research Program; Notice of
Meeting
The ACRS Subcommittee on Safety
Research Program will hold a meeting
on April 16–17, 2009, Room T–2B3,
11545 Rockville Pike, Rockville,
Maryland.
The entire meeting will be open to
public attendance.
The agenda for the subject meeting
shall be as follows:
Thursday, April 16, 2009—8:30 a.m.
until the conclusion of business
Friday, April 17, 2009—8:30 a.m.–12
p.m.
The Subcommittee will discuss
seismic-related issues. The
Subcommittee will hear presentations
by and hold discussions with
representatives of the NRC staff, and
other interested persons regarding this
matter. 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, Mr. Michael Lee
(Telephone: 301–415–6887) five days
prior to the meeting, if possible, so that
appropriate arrangements can be made.
Electronic recordings will be permitted.
Detailed procedures for the conduct of
and participation in ACRS meetings
were published in the Federal Register
on October 6, 2008 (73 FR 58268–
58269).
Further information regarding this
meeting can be obtained by contacting
the Designated Federal Official between
8:30 a.m. and 5:15 p.m. (ET). Persons
planning to attend this meeting are
urged to contact the above named
individual at least two working days
prior to the meeting to be advised of any
potential changes to the agenda.
Dated: March 24, 2009.
Antonio Dias,
Chief, Reactor Safety Branch B, Advisory
Committee on Reactor Safeguards.
[FR Doc. E9–7276 Filed 3–30–09; 8:45 am]
BILLING CODE 7590–01–P
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Sunshine Notice
AGENCY HOLDING THE MEETINGS:
Regulatory Commission.
VerDate Nov<24>2008
14:35 Mar 30, 2009
Jkt 217001
PO 00000
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Weeks of March 30, April 6, 13,
20, 27, May 4, 2009.
PLACE: Commissioners’ Conference
Room, 11555 Rockville Pike, Rockville,
Maryland.
STATUS: Public and closed.
DATE:
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Nuclear
Week of March 30, 2009
There are no meetings scheduled for
the week of March 30, 2009.
Week of April 6, 2009—Tentative
There are no meetings scheduled for
the week of April 6, 2009.
Week of April 13, 2009—Tentative
Wednesday, April 15, 2009.
9:30 a.m. Briefing on NRC Corporate
Support (Public Meeting) (Contact:
Karen Olive, 301–415–2276)
This meeting will be Web cast live at
the Web address—https://www.nrc.gov.
Thursday, April 16, 2009
1:30 p.m. Briefing on Human Capital
and EEO (Public Meeting) (Contact:
Kristin Davis, 301–492–2266)
This meeting will be Web cast live at
the Web address—https://www.nrc.gov.
Friday, April 17, 2009.
9:30 a.m. Briefing on Low Level
Radioactive Waste—Part 1 (Public
Meeting) (Contact: Patricia Swain, 301–
415–5405)
This meeting will be Web cast live at
the Web address—https://www.nrc.gov.
Friday, April 17, 2009.
1:30 p.m. Briefing on Low Level
Radioactive Waste—Part 2 (Public
Meeting) (Contact: Patricia Swain, 301–
415–5405)
This meeting will be Web cast live at
the Web address—https://www.nrc.gov.
Week of April 20, 2009—Tentative
Thursday, April 23, 2009
2 p.m. Briefing on Radioactive
Source Security (Public Meeting)
(Contact: Kim Lukes, 301–415–6701)
This meeting will be Web cast live at
the Web address—https://www.nrc.gov.
Week of April 27, 2009—Tentative
There are no meetings scheduled for
the week of April 27, 2009.
Week of May 4, 2009—Tentative
There are no meetings scheduled for
the week of May 4, 2009.
*
*
*
*
*
* The schedule for Commission
meetings is subject to change on short
notice. To verify the status of meetings,
call (recording)—(301) 415–1292.
Contact person for more information:
Rochelle Bavol, (301) 415–1651.
*
*
*
*
*
E:\FR\FM\31MRN1.SGM
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Agencies
[Federal Register Volume 74, Number 60 (Tuesday, March 31, 2009)]
[Notices]
[Pages 14594-14596]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-7153]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 030-33421; NRC-2009-0143]
Notice of Availability of Environmental Assessment and Finding of
No Significant Impact for License Amendment to Byproduct Nuclear
Materials License No. 29-30119-01, for Termination of the License and
Unrestricted Release of the Medarex, Incorporated's Facility in
Bloomsbury, NJ
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of Environmental Assessment and Finding of No
Significant Impact for License Amendment.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Dennis Lawyer, Health Physicist,
Commercial and R&D Branch, Division of Nuclear Materials Safety, Region
I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610-
337-5366; fax number 610-337-5269; or by e-mail: dennis.lawyer@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. 29-
30119-01. This license is held by Medarex, Incorporated (the Licensee),
for its facilities located at 519 Route 173 West, Bloomsbury, New
Jersey (the Facility). Issuance of the amendment would authorize
release of the Facility for unrestricted use and termination of the NRC
license. The Licensee requested this action in a letter dated December
1, 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 December 1, 2008,
license amendment request, resulting in release of the Facility for
unrestricted use and the termination of its NRC materials license.
License No. 29-30119-01 was issued on February 28, 1994, pursuant
[[Page 14595]]
to 10 CFR Part 30, and has been amended periodically since that time.
This license authorized the Licensee to use unsealed byproduct material
for purposes of conducting research and development activities on
laboratory bench tops and in hoods.
The Facility is situated within a 164,130 square foot building, and
consists of general office space and laboratories. The Facility is
located in a mixed rural/residential area. Within the Facility, use of
licensed materials with a half-life of greater than 120 days was
confined to Room 115A. The area of Room 115A totaled 229 square feet.
In March 2006, the Licensee ceased licensed activities and
initiated a survey and decontamination of the Facility. Based on the
Licensee's historical knowledge of the site and the conditions of the
Facility, 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 Facility and
provided information to the NRC to demonstrate that it meets the
criteria in Subpart E of 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
Facility, and seeks the unrestricted use of its Facility 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
Facility shows that such activities involved use of the following
radionuclides with half-lives greater than 120 days: Hydrogen 3. Prior
to performing the final status survey, the Licensee conducted
decontamination activities, as necessary, in the areas of the Facility
affected by this radionuclide.
The Licensee conducted a final status survey in November 2008. This
survey covered Room 115A. The final status survey report was attached
to the Licensee's amendment request dated December 1, 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 criterion in 10
CFR 20.1402. These DCGLs define the maximum amount of residual
radioactivity on building surfaces, equipment, and materials 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 Facility. 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 Facility. 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 Facility for
unrestricted use and the termination of the NRC materials license is in
compliance with 10 CFR 20.1402. Based on its review, the staff
considered the impact of the residual radioactivity at the Facility 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 Facility 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 New
Jersey Department of Environmental Protection for review on January 28,
2009. On February 26, 2009, the New Jersey Department of Environmental
Protection responded by letter. The State agreed with the conclusions
of the EA but noted there was use of radioactive material in an
additional area, specifically Room 145A. NRC noted that while the
Licensee included Room 145A in its final status survey, the half-life
of radioactive materials used in Room 145A did not exceed 120 days.
Therefore, in accordance with the categorical exclusion described in 10
CFR 51.22(c)(20), no environmental assessment is required for Room
145A.
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
[[Page 14596]]
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 Document 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;'' and
5. Medarex, Incorporated termination request letter dated December
1, 2008 (ML083510774).
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.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 Region I, 475 Allendale Road, King of Prussia, PA this
24th day of March.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety,
Region I.
[FR Doc. E9-7153 Filed 3-30-09; 8:45 am]
BILLING CODE 7590-01-P