Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Nuclear Materials License No. 06-30693-01, for Termination of the License and Unrestricted Release of the Protometrix-an Invitrogen Company Facility in Branford, CT, 25582-25583 [E9-12402]
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Federal Register / Vol. 74, No. 101 / Thursday, May 28, 2009 / Notices
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I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is considering the
issuance of an amendment terminating
Byproduct Materials License No. 06–
30693–01. This license is held by
Protometrix—an Invitrogen Company
(the Licensee), for its facility located at
688 East Main Street, Branford,
Connecticut (the Facility). Issuance of
the amendment would authorize release
of the Facility for unrestricted use and
terminate the NRC license. The Licensee
requested this action in a letter dated
March 12, 2009. 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, and the
license will be terminated, following the
publication of this FONSI and EA in the
Federal Register.
Dated: May 20, 2009.
Douglas A. Comstock,
Director, Innovative Partnerships Program.
[FR Doc. E9–12315 Filed 5–27–09; 8:45 am]
II. Environmental Assessment
BILLING CODE P
NUCLEAR REGULATORY
COMMISSION
[NRC–2009–0217; Docket No. 030–35868]
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment to Byproduct Nuclear
Materials License No. 06–30693–01, for
Termination of the License and
Unrestricted Release of the
Protometrix—an Invitrogen Company
Facility in Branford, CT
AGENCY: Nuclear Regulatory
Commission.
ACTION: Issuance of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment and Termination.
FOR FURTHER INFORMATION CONTACT:
Thomas K. Thompson, Sr. Health
Physicist, Commercial and R&D Branch,
Division of Nuclear Materials Safety,
Region I, 475 Allendale Road, King of
Prussia, Pennsylvania 19406; telephone
(610) 337–5303; fax number (610) 337–
5269; or by e-mail:
Thomas.Thompson@nrc.gov.
SUPPLEMENTARY INFORMATION:
VerDate Nov<24>2008
17:11 May 27, 2009
Jkt 217001
Identification of Proposed Action
The proposed action would approve
the Licensee’s March 12, 2009, license
amendment and termination request,
resulting in release of the Facility for
unrestricted use and the termination of
its NRC materials license. License No.
06–30693–01 was issued on November
19, 2001, pursuant to 10 CFR part 30,
and has been amended periodically
since that time. This license authorizes
the Licensee to use hydrogen-3, carbon14, phosphorus-32, phosphorus-33,
sulfur-35, and iodine 125 for conducting
research and development.
The Facility is a one story building of
approximately 13,787 square feet,
consisting of warehouse spaces, office
spaces, and laboratories. Within the
Facility, use of licensed materials was
largely confined to two small
laboratories with a total area of
approximately 330 square feet. The
Facility is located in an industrial area.
Within the Facility, the radionuclides of
concern were hydrogen-3 and carbon-14
because the half-life of these isotopes is
greater than 120 days.
In January 2009, the Licensee last
handled byproduct materials, ceased
licensed activities, and initiated a
survey of the affected areas 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 the NRC-approved
PO 00000
Frm 00104
Fmt 4703
Sfmt 4703
operating radiation safety procedures,
would be 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 a
half-life greater than 120 days:
hydrogen-3 and carbon-14.
The Licensee conducted a final status
survey in January 2009. This survey
covered the areas of use in the Facility.
The final status survey report was
received March 12, 2009. The Licensee
demonstrated 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 Decommissioning
Guidance,’’ Volume 2. The
radionuclide-specific derived
concentration guideline levels (DCGLs),
developed 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, 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
E:\FR\FM\28MYN1.SGM
28MYN1
Federal Register / Vol. 74, No. 101 / Thursday, May 28, 2009 / Notices
Criteria for License Termination of NRCLicensed Nuclear Facilities’’ Volumes
1–3 (NUREG–1496) (ADAMS Accession
Nos. 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 and termination 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 confirms that
the Facility meets the requirements of
10 CFR 20.1402 for unrestricted release
and for license termination.
Additionally, denying the amendment
and termination 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.
VerDate Nov<24>2008
17:11 May 27, 2009
Jkt 217001
Agencies and Persons Consulted
NRC provided a draft of this
Environmental Assessment to the State
of Connecticut, Department of
Environmental Protection, Division of
Radiation, for review on April 9, 2009.
The State replied by electronic mail on
April 17, 2009, indicating they agreed
with the conclusions of the
Environmental Assessment.
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 termination 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. NRC License No. 06–30693–01
Amendment 05 issued January 15, 2009
(ADAMS Accession No. ML013270325);
2. Termination request dated March
12, 2009 (ADAMS Accession No.
ML090780841);
3. Additional information on
termination request dated March 20,
2009 (ADAMS Accession No.
ML090970767);
4. NUREG–1757, ‘‘Consolidated
NMSS Decommissioning Guidance,’’
Volume 2;
5. Title 10, Code of Federal
Regulations, Part 20, Subpart E,
‘‘Radiological Criteria for License
Termination’’;
PO 00000
Frm 00105
Fmt 4703
Sfmt 4703
25583
6. Title 10, Code of Federal
Regulations, Part 51, ‘‘Environmental
Protection Regulations for Domestic
Licensing and Related Regulatory
Functions’’;
7. NUREG–1496, ‘‘Generic
Environmental Impact Statement in
Support of Rulemaking on Radiological
Criteria for License Termination of NRCLicensed Nuclear Facilities,’’ Volumes
1–3.
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 1F21, One
White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR
reproduction contractor will copy
documents for a fee.
Dated at 475 Allendale Road, King of
Prussia, PA this 19th day of May 2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial & R&D, Division of
Nuclear Materials Safety, Region I.
[FR Doc. E9–12402 Filed 5–27–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
Advisory Committee on Reactor
Safeguards (ACRS); Meeting of the
ACRS Subcommittee on ESBWR;
Notice of Meeting
The ACRS Subcommittee on the
Economic Simplified Boiling Water
Reactor (ESBWR) will hold a meeting on
June 17–18, 2009, 11545 Rockville Pike,
Room T2–B3 Rockville, Maryland.
The entire meeting will be open to
public attendance, with the exception of
a portion that may be closed to protect
information that is proprietary to
General Electric—Hitachi Nuclear
Americas, LLC (GEH) and its contractors
pursuant to 5 U.S.C. 552b(c)(4).
The agenda for the subject meeting
shall be as follows:
Wednesday, June 17, 2009–8:30 a.m.–5
p.m.
Thursday, June 18, 2009–8:30 a.m.–5
p.m.
The Subcommittee will review the
resolution of Open Items associated
with ESBWR design certification related
to containment issues and review the
Safety Evaluation Report with Open
Items associated with the North Anna
Combined License Application
referencing the ESBWR design. The
Subcommittee will hear presentations
E:\FR\FM\28MYN1.SGM
28MYN1
Agencies
[Federal Register Volume 74, Number 101 (Thursday, May 28, 2009)]
[Notices]
[Pages 25582-25583]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-12402]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2009-0217; Docket No. 030-35868]
Notice of Availability of Environmental Assessment and Finding of
No Significant Impact for License Amendment to Byproduct Nuclear
Materials License No. 06-30693-01, for Termination of the License and
Unrestricted Release of the Protometrix--an Invitrogen Company Facility
in Branford, CT
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of Environmental Assessment and Finding of No
Significant Impact for License Amendment and Termination.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Thomas K. Thompson, Sr. Health
Physicist, Commercial and R&D Branch, Division of Nuclear Materials
Safety, Region I, 475 Allendale Road, King of Prussia, Pennsylvania
19406; telephone (610) 337-5303; fax number (610) 337-5269; or by e-
mail: Thomas.Thompson@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) is considering the
issuance of an amendment terminating Byproduct Materials License No.
06-30693-01. This license is held by Protometrix--an Invitrogen Company
(the Licensee), for its facility located at 688 East Main Street,
Branford, Connecticut (the Facility). Issuance of the amendment would
authorize release of the Facility for unrestricted use and terminate
the NRC license. The Licensee requested this action in a letter dated
March 12, 2009. 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, and the license
will be terminated, 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 12, 2009,
license amendment and termination request, resulting in release of the
Facility for unrestricted use and the termination of its NRC materials
license. License No. 06-30693-01 was issued on November 19, 2001,
pursuant to 10 CFR part 30, and has been amended periodically since
that time. This license authorizes the Licensee to use hydrogen-3,
carbon-14, phosphorus-32, phosphorus-33, sulfur-35, and iodine 125 for
conducting research and development.
The Facility is a one story building of approximately 13,787 square
feet, consisting of warehouse spaces, office spaces, and laboratories.
Within the Facility, use of licensed materials was largely confined to
two small laboratories with a total area of approximately 330 square
feet. The Facility is located in an industrial area. Within the
Facility, the radionuclides of concern were hydrogen-3 and carbon-14
because the half-life of these isotopes is greater than 120 days.
In January 2009, the Licensee last handled byproduct materials,
ceased licensed activities, and initiated a survey of the affected
areas 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 the
NRC-approved operating radiation safety procedures, would be 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 a half-life greater than 120 days: hydrogen-3 and
carbon-14.
The Licensee conducted a final status survey in January 2009. This
survey covered the areas of use in the Facility. The final status
survey report was received March 12, 2009. The Licensee demonstrated
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 Decommissioning Guidance,'' Volume 2. The
radionuclide-specific derived concentration guideline levels (DCGLs),
developed 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, 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
[[Page 25583]]
Criteria for License Termination of NRC-Licensed Nuclear Facilities''
Volumes 1-3 (NUREG-1496) (ADAMS Accession Nos. 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
and termination 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 confirms that the Facility
meets the requirements of 10 CFR 20.1402 for unrestricted release and
for license termination. Additionally, denying the amendment and
termination 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 Connecticut, Department of Environmental Protection, Division of
Radiation, for review on April 9, 2009. The State replied by electronic
mail on April 17, 2009, indicating they agreed with the conclusions of
the Environmental Assessment.
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 termination 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. NRC License No. 06-30693-01 Amendment 05 issued January 15, 2009
(ADAMS Accession No. ML013270325);
2. Termination request dated March 12, 2009 (ADAMS Accession No.
ML090780841);
3. Additional information on termination request dated March 20,
2009 (ADAMS Accession No. ML090970767);
4. NUREG-1757, ``Consolidated NMSS Decommissioning Guidance,''
Volume 2;
5. Title 10, Code of Federal Regulations, Part 20, Subpart E,
``Radiological Criteria for License Termination'';
6. Title 10, Code of Federal Regulations, Part 51, ``Environmental
Protection Regulations for Domestic Licensing and Related Regulatory
Functions'';
7. NUREG-1496, ``Generic Environmental Impact Statement in Support
of Rulemaking on Radiological Criteria for License Termination of NRC-
Licensed Nuclear Facilities,'' Volumes 1-3.
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
1F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852.
The PDR reproduction contractor will copy documents for a fee.
Dated at 475 Allendale Road, King of Prussia, PA this 19th day
of May 2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial & R&D, Division of Nuclear Materials Safety, Region
I.
[FR Doc. E9-12402 Filed 5-27-09; 8:45 am]
BILLING CODE 7590-01-P