Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment To Byproduct Materials License No. 21-01443-06, for Unrestricted Release of the Parke-Davis Warner-Lambert Facility in Plymouth, MI, 57969-57970 [E7-20050]
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Federal Register / Vol. 72, No. 196 / Thursday, October 11, 2007 / Notices
NUCLEAR REGULATORY
COMMISSION
[Docket No. 030–04794]
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment To Byproduct Materials
License No. 21–01443–06, for
Unrestricted Release of the ParkeDavis Warner-Lambert Facility in
Plymouth, MI
Nuclear Regulatory
Commission.
ACTION: Issuance of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment.
AGENCY:
FOR FURTHER INFORMATION CONTACT:
William Snell, Senior Health Physicist,
Decommissioning Branch, Division of
Nuclear Materials Safety, Region III,
U.S. Nuclear Regulatory Commission,
2443 Warrenville Road, Lisle, Illinois
60532; telephone: (630) 829–9871; fax
number: (630) 515–1259; or by e-mail at
wgs@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. 21–
01443–06. This license is held by
Warner-Lambert, LLC (the Licensee),
which is a wholly owned subsidiary of
Pfizer, Inc., for its Parke-Davis Plymouth
Township facility (the Facility) located
at 46701 Commerce Center Drive in
Plymouth, Michigan. Issuance of the
amendment would authorize release of
the Facility for unrestricted use. The
Licensee requested this action in a letter
dated June 14, 2007 (ADAMS Accession
No. ML071700495). 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.
rwilkins on PROD1PC63 with NOTICES
II. Environmental Assessment
Identification of Proposed Action
The proposed action would approve
the Licensee’s June 14, 2007, license
amendment request, resulting in release
of the Facility for unrestricted use.
License No. 21–01443–06 was issued on
VerDate Aug<31>2005
16:09 Oct 10, 2007
Jkt 214001
April 20, 1959, pursuant to 10 CFR Part
30, and has been amended periodically
since that time. Warner-Lambert was
first licensed to use byproduct materials
at its Parke-Davis facility on August 9,
1999. This license authorized the
Licensee to use byproduct materials for
purposes of conducting research and
development.
The Facility is approximately a 60,000
ft2, one-story steel frame building with
concrete, glass and metal exterior walls;
and consists of office space and
laboratories. The Facility is located in a
mixed residential/commercial area.
Within the Facility, use of licensed
materials was primarily confined to
laboratories 1311, 1325, 1402, 1406 and
1442. On May 11, 2007, the Licensee
ceased licensed activities and initiated a
survey and decontamination of the
Facility on May 14, 2007. On May 23,
2007, the Licensee completed removal
of licensed radioactive material from 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 radiation safety
procedures, were required. The Licensee
was not required to submit a
decommissioning plan to the NRC. 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.
Need for the Proposed Action
The licensee has ceased conducting
licensed activities at the Facility, and it
seeks the unrestricted use of its Facility.
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: Hydrogen3 and carbon-14. Prior to performing the
final status survey, the Licensee
conducted decontamination activities,
as necessary, in the areas of the Facility
affected by these radionuclides.
The Licensee conducted a final status
survey on May 24, 2007. This survey
covered 21,600 square feet of surface
area considered to have a low potential
for delivering a dose above the release
criteria, and included the drain system,
ventilation exhaust system, and vacuum
system. No areas were considered to
have a potential for delivering a dose
above the release criteria. The final
status survey report was attached to the
Licensee’s amendment request dated
June 14, 2007. The Licensee elected to
PO 00000
Frm 00061
Fmt 4703
Sfmt 4703
57969
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, 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
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 NRCLicensed 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 is in compliance with 10 CFR
20.1402. The NRC has found no other
activities in the area that could result in
cumulative environmental impacts.
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.
E:\FR\FM\11OCN1.SGM
11OCN1
57970
Federal Register / Vol. 72, No. 196 / Thursday, October 11, 2007 / Notices
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. 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.
rwilkins on PROD1PC63 with NOTICES
Agencies and Persons Consulted
NRC provided a draft of this
Environmental Assessment to the
Michigan Department of Environmental
Quality (DEQ) for review on August 23,
2007. On August 24, 2007, Mr. Bob
Skowronek, Chief, Radioactive Material
and Medical Waste Unit, with the
Michigan DEQ, responded by email. 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
VerDate Aug<31>2005
16:09 Oct 10, 2007
Jkt 214001
that a Finding of No Significant Impact
is appropriate.
NUCLEAR REGULATORY
COMMISSION
IV. Further Information
Notice of Opportunity To Comment on
Model Safety Evaluation, Model No
Significant Hazards Determination, and
Model Application for Licensees That
Wish To Adopt TSTF–478, Revision 2,
‘‘BWR Technical Specification
Changes That Implement the Revised
Rule for Combustible Gas Control’’
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. Carol Lentz, Pfizer, Inc., letter to
Patricia Pelke, U.S. Nuclear Regulatory
Commission, June 14, 2007 (ADAMS
Accession No. ML071700495);
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. NUREG–1757, ‘‘Consolidated
NMSS Decommissioning Guidance.’’
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 Lisle, Illinois, this 27th day of
September 2007.
For the Nuclear Regulatory Commission.
Patrick Louden,
Chief, Decommissioning Branch, Division of
Nuclear Materials Safety, Region III.
[FR Doc. E7–20050 Filed 10–10–07; 8:45 am]
Frm 00062
Fmt 4703
SUMMARY: Notice is hereby given that
the staff of the Nuclear Regulatory
Commission (NRC) has prepared a
model safety evaluation (SE) and a
model application related to the
modification of containment
combustible gas control requirements in
technical specifications (TS) for Boiling
Water Reactors (BWR). The NRC staff
has also prepared a model nosignificant-hazards-consideration
(NSHC) determination related to this
matter. The purpose of these models is
to permit the NRC to efficiently process
license amendment applications that
propose to adopt TSTF–478, Revision 2,
‘‘BWR Technical Specification Changes
that Implement the Revised Rule for
Combustible Gas Control.’’ TSTF–478,
Revision 2, deletes Standard Technical
Specification (STS) 3.6.3.3,
‘‘Containment Atmosphere Dilution
(CAD) System’’ and modifies STS
3.6.3.1, ‘‘Drywell Cooling System Fans,’’
in NUREG–1433, ‘‘Standard Technical
Specifications General Electric Plants,
BWR/4, Rev. 3,’’ to establish TS for
containment combustible gas control
requirements as permitted by revised 10
CFR 50.44. Licensees of nuclear power
reactors to which the models apply
could then request amendments,
confirming the applicability of the SE
and NSHC determination to their plants.
The NRC staff is requesting comment on
the model SE, model application, and
model NSHC determination prior to
announcing their availability for
referencing in license amendment
applications.
The comment period expires
November 13, 2007. Comments received
after this date will be considered if it is
practical to do so, but the Commission
is able to ensure consideration only of
comments received on or before this
date.
DATES:
Comments may be
submitted either electronically or via
U.S. mail. Submit written comments to
Chief, Rulemaking, Directives and
Editing Branch, Division of
BILLING CODE 7590–01–P
PO 00000
Nuclear Regulatory
Commission.
ACTION: Request for comment.
AGENCY:
ADDRESSES:
Sfmt 4703
E:\FR\FM\11OCN1.SGM
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]]>Agencies
[Federal Register Volume 72, Number 196 (Thursday, October 11, 2007)]
[Notices]
[Pages 57969-57970]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-20050]
[[Page 57969]]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 030-04794]
Notice of Availability of Environmental Assessment and Finding of
No Significant Impact for License Amendment To Byproduct Materials
License No. 21-01443-06, for Unrestricted Release of the Parke-Davis
Warner-Lambert Facility in Plymouth, MI
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of Environmental Assessment and Finding of No
Significant Impact for License Amendment.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: William Snell, Senior Health
Physicist, Decommissioning Branch, Division of Nuclear Materials
Safety, Region III, U.S. Nuclear Regulatory Commission, 2443
Warrenville Road, Lisle, Illinois 60532; telephone: (630) 829-9871; fax
number: (630) 515-1259; or by e-mail at wgs@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. 21-
01443-06. This license is held by Warner-Lambert, LLC (the Licensee),
which is a wholly owned subsidiary of Pfizer, Inc., for its Parke-Davis
Plymouth Township facility (the Facility) located at 46701 Commerce
Center Drive in Plymouth, Michigan. Issuance of the amendment would
authorize release of the Facility for unrestricted use. The Licensee
requested this action in a letter dated June 14, 2007 (ADAMS Accession
No. ML071700495). 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 June 14, 2007,
license amendment request, resulting in release of the Facility for
unrestricted use. License No. 21-01443-06 was issued on April 20, 1959,
pursuant to 10 CFR Part 30, and has been amended periodically since
that time. Warner-Lambert was first licensed to use byproduct materials
at its Parke-Davis facility on August 9, 1999. This license authorized
the Licensee to use byproduct materials for purposes of conducting
research and development.
The Facility is approximately a 60,000 ft\2\, one-story steel frame
building with concrete, glass and metal exterior walls; and consists of
office space and laboratories. The Facility is located in a mixed
residential/commercial area. Within the Facility, use of licensed
materials was primarily confined to laboratories 1311, 1325, 1402, 1406
and 1442. On May 11, 2007, the Licensee ceased licensed activities and
initiated a survey and decontamination of the Facility on May 14, 2007.
On May 23, 2007, the Licensee completed removal of licensed radioactive
material from 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 radiation safety procedures, were required. The Licensee was
not required to submit a decommissioning plan to the NRC. 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.
Need for the Proposed Action
The licensee has ceased conducting licensed activities at the
Facility, and it seeks the unrestricted use of its Facility.
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 and
carbon-14. Prior to performing the final status survey, the Licensee
conducted decontamination activities, as necessary, in the areas of the
Facility affected by these radionuclides.
The Licensee conducted a final status survey on May 24, 2007. This
survey covered 21,600 square feet of surface area considered to have a
low potential for delivering a dose above the release criteria, and
included the drain system, ventilation exhaust system, and vacuum
system. No areas were considered to have a potential for delivering a
dose above the release criteria. The final status survey report was
attached to the Licensee's amendment request dated June 14, 2007. 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, 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 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 is in compliance with 10 CFR 20.1402. The NRC has
found no other activities in the area that could result in cumulative
environmental impacts. 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.
[[Page 57970]]
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.
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
Michigan Department of Environmental Quality (DEQ) for review on August
23, 2007. On August 24, 2007, Mr. Bob Skowronek, Chief, Radioactive
Material and Medical Waste Unit, with the Michigan DEQ, responded by
email. 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 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. Carol Lentz, Pfizer, Inc., letter to Patricia Pelke, U.S.
Nuclear Regulatory Commission, June 14, 2007 (ADAMS Accession No.
ML071700495);
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. NUREG-1757, ``Consolidated NMSS Decommissioning Guidance.''
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 Lisle, Illinois, this 27th day of September 2007.
For the Nuclear Regulatory Commission.
Patrick Louden,
Chief, Decommissioning Branch, Division of Nuclear Materials Safety,
Region III.
[FR Doc. E7-20050 Filed 10-10-07; 8:45 am]
BILLING CODE 7590-01-P
