Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Materials License No. 29-00040-10, for Termination of the License and Unrestricted Release of the Honeywell International, Incorporated Facility in Morristown, NJ, 4736-4737 [E7-1645]
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4736
Federal Register / Vol. 72, No. 21 / Thursday, February 1, 2007 / Notices
Decommissioning/Remediation Plan .............................................................................................................................................
Receipt of Decommissioning Plan .................................................................................................................................................
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, PA, this 23rd day of January
2007.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I.
[FR Doc. E7–1647 Filed 1–31–07; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 03011981]
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment to Byproduct Materials
License No. 29–00040–10, for
Termination of the License and
Unrestricted Release of the Honeywell
International, Incorporated Facility in
Morristown, NJ
Nuclear Regulatory
Commission.
ACTION: Issuance of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment.
AGENCY:
FOR FURTHER INFORMATION CONTACT:
rwilkins on PROD1PC63 with NOTICES
Dennis Lawyer, Health Physicist,
Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region 1,
475 Allendale Road, King of Prussia,
Pennsylvania; telephone 610–337–5366;
fax number 610–337–5393; or by e-mail:
drl1@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–
00040–10. This license is held by
Honeywell International, Incorporated
(the Licensee), for its facility located at
101 Columbia Road in Morristown, New
Jersey (the Facility). Issuance of the
VerDate Aug<31>2005
16:47 Jan 31, 2007
Jkt 211001
amendment would authorize release of
the Facility for unrestricted use and
termination of the NRC license. The
Licensee requested this action in an
amendment request dated September 8,
2005. 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 September 8, 2005,
license amendment request, resulting in
release of the Facility for unrestricted
use and the termination of its NRC
materials license. License No. 29–
00040–10 was issued on August 21,
1973, 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 on laboratory bench tops and
in hoods.
The Facility is situated on 150 acres
of land and consists of office buildings,
laboratory buildings, and support
buildings. The Facility is located in a
mixed industrial commercial area with
some residential. Within the Facility,
use of licensed materials was confined
to an area of 1675 square feet within the
DEV Building, specifically Laboratories
4, 7, and 8.
On September 18, 2003, 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
PO 00000
Frm 00057
Fmt 4703
Sfmt 4703
ML062760618
ML062930051
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 unsealed 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 October 3, 2006. This survey
covered DEV Building, Laboratories 4, 7,
and 8. The final status survey report was
submitted with the Licensee’s letter
dated October 24, 2006. 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 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 NRCLicensed Nuclear Facilities’’ (NUREG–
E:\FR\FM\01FEN1.SGM
01FEN1
Federal Register / Vol. 72, No. 21 / Thursday, February 1, 2007 / Notices
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 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.
rwilkins on PROD1PC63 with NOTICES
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 Aug<31>2005
16:47 Jan 31, 2007
Jkt 211001
Agencies and Persons Consulted
NRC provided a draft of this
Environmental Assessment to the State
of New Jersey’s Department of
Environmental Safety and Health for
review on December 18, 2006. On
December 26, 2006, the State of New
Jersey responded by letter, agreeing 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. 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. Honeywell International Inc.,
Termination Request Letter dated
PO 00000
Frm 00058
Fmt 4703
Sfmt 4703
4737
September 8, 2005, under cover letter
dated August 31, 2005 [ML052590382];
6. Honeywell International Inc.,
Deficiency Response Letter dated
November 18, 2005 [ML053250525];
7. Honeywell International Inc.,
Deficiency Response Letter dated March
13, 2006 [ML060820354];
8. Honeywell International Inc.,
Deficiency Response Letter dated
October 24, 2006 [ML063050527];
9. Honeywell International Inc.,
Deficiency Facsimile dated November
26, 2006 [ML063320313].
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, PA this 23rd day of January,
2007.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region 1.
[FR Doc. E7–1645 Filed 1–31–07; 8:45 am]
BILLING CODE 7590–01–P
SECURITIES AND EXCHANGE
COMMISSION
Proposed Collection; Comment
Request
Upon Written Request, Copies Available
From: Securities and Exchange
Commission, Office of Filings and
Information Services, Washington, DC
20549
Extension:
Rule 19b–4(e) and Form 19b–4(e), SEC File
No. 270–447, OMB Control No. 3235–
0504.
Notice is hereby given that pursuant
to the Paperwork Reduction Act of 1995
(44 U.S.C. 3501 et seq.) the Securities
and Exchange Commission
(‘‘Commission’’) intends to submit to
the Office of Management and Budget
requests for extension of the previously
approved collections of information
discussed below. The Code of Federal
Regulation citation to this collection of
information is 17 CFR 240.19b–4(e)
under the Securities Exchange Act of
1934 (17 U.S.C. 78a et seq.) (the ‘‘Act’’).
Rule 19b–4(e) permits a selfregulatory organization (‘‘SRO’’) to
E:\FR\FM\01FEN1.SGM
01FEN1
]]>Agencies
[Federal Register Volume 72, Number 21 (Thursday, February 1, 2007)]
[Notices]
[Pages 4736-4737]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-1645]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 03011981]
Notice of Availability of Environmental Assessment and Finding of
No Significant Impact for License Amendment to Byproduct Materials
License No. 29-00040-10, for Termination of the License and
Unrestricted Release of the Honeywell International, Incorporated
Facility in Morristown, 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
1, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610-
337-5366; fax number 610-337-5393; or by e-mail: drl1@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-
00040-10. This license is held by Honeywell International, Incorporated
(the Licensee), for its facility located at 101 Columbia Road in
Morristown, 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 an amendment
request dated September 8, 2005. 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 September 8, 2005,
license amendment request, resulting in release of the Facility for
unrestricted use and the termination of its NRC materials license.
License No. 29-00040-10 was issued on August 21, 1973, 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
on laboratory bench tops and in hoods.
The Facility is situated on 150 acres of land and consists of
office buildings, laboratory buildings, and support buildings. The
Facility is located in a mixed industrial commercial area with some
residential. Within the Facility, use of licensed materials was
confined to an area of 1675 square feet within the DEV Building,
specifically Laboratories 4, 7, and 8.
On September 18, 2003, 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
unsealed 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 October 3, 2006.
This survey covered DEV Building, Laboratories 4, 7, and 8. The final
status survey report was submitted with the Licensee's letter dated
October 24, 2006. 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 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-
[[Page 4737]]
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 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 New Jersey's Department of Environmental Safety and Health for
review on December 18, 2006. On December 26, 2006, the State of New
Jersey responded by letter, agreeing 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. 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. Honeywell International Inc., Termination Request Letter dated
September 8, 2005, under cover letter dated August 31, 2005
[ML052590382];
6. Honeywell International Inc., Deficiency Response Letter dated
November 18, 2005 [ML053250525];
7. Honeywell International Inc., Deficiency Response Letter dated
March 13, 2006 [ML060820354];
8. Honeywell International Inc., Deficiency Response Letter dated
October 24, 2006 [ML063050527];
9. Honeywell International Inc., Deficiency Facsimile dated
November 26, 2006 [ML063320313].
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, PA this
23rd day of January, 2007.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety,
Region 1.
[FR Doc. E7-1645 Filed 1-31-07; 8:45 am]
BILLING CODE 7590-01-P
