Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendments to Byproduct Materials License No. 29-00170-03 and Source Materials License No. SMB-1260, Incorporating the Decommissioning Plan for Bell Laboratories Murray Hill Facility in Murray Hill, NJ, 39346-39348 [E9-18820]
Download as PDF
39346
Federal Register / Vol. 74, No. 150 / Thursday, August 6, 2009 / Notices
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 28th day of July
2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I.
[FR Doc. E9–18819 Filed 8–5–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2008–0639; Docket Nos. 030–05224
and 040–08478]
Notice of Availability of Environmental
Assessment and Finding of No
Significant Impact for License
Amendments to Byproduct Materials
License No. 29–00170–03 and Source
Materials License No. SMB–1260,
Incorporating the Decommissioning
Plan for Bell Laboratories Murray Hill
Facility in Murray Hill, NJ
AGENCY: Nuclear Regulatory
Commission.
ACTION: Issuance of Environmental
Assessment and Finding of No
Significant Impact for License
Amendment.
FOR FURTHER INFORMATION CONTACT:
Steve Hammann, Health Physicist,
Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I,
475 Allendale Road, King of Prussia,
Pennsylvania; telephone 610–337–5399;
fax number 610–337–5269; or by e-mail:
stephen.hammann@nrc.gov.
SUPPLEMENTARY INFORMATION:
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I. Introduction
The U.S. Nuclear Regulatory
Commission (NRC) is considering the
issuance of license amendments to
Byproduct Materials License No. 29–
00170–03 and Source Materials License
No. SMB–1260. The licenses are held by
Bell Laboratories (the Licensee), for its
Murray Hill Facility, located at 600
Mountain Avenue in Murray Hill, New
Jersey (the Facility). Issuance of the
amendments would incorporate the
Decommissioning Plan (DP) into the
licenses to allow completion of
decommissioning activities at the site
and subsequent release of the Facility,
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17:04 Aug 05, 2009
Jkt 217001
except one room in the Radiation Lab,
for unrestricted use and the termination
of its NRC materials licenses. The room
which is not being released is covered
by NRC License No. 29–00170–08. The
NRC has evaluated and approved the
Licensee’s DP. The findings of this
evaluation are documented in a Safety
Evaluation Report which will be issued
along with the amendments. The
Licensee requested these actions in a
letter dated June 12, 2008. The
Licensee’s amendment requests were
noted in the Federal Register on
December 8, 2008 (73 FR 74529). This
Federal Register notice also provided an
opportunity for a hearing on these
licensing actions. No hearing requests
were received. The NRC has prepared
an Environmental Assessment (EA) in
support of the proposed actions 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 actions. The amendments
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 actions would approve
the Licensee’s June 12, 2008 license
amendment requests to incorporate the
DP into the licenses, resulting in
decommissioning of the facility and
subsequent release of the Facility,
except one room in the Radiation Lab,
for unrestricted use and the termination
of its NRC materials licenses. The room
which is not being released is covered
by NRC License No. 29–00170–08.
License No. 29–00170–03 was issued on
January 25, 1957, pursuant to 10 CFR
Part 30, and License No. SMB–1260 was
issued on December 2, 1975, pursuant to
10 CFR Part 40. Both licenses have been
amended periodically since the issue
dates. These licenses authorized the
Licensee to use sealed and unsealed
byproduct material and source material
for the purpose of conducting research
and development activities on
laboratory bench tops and in hoods.
The Facility is situated on 196 acres
and encompasses fifteen buildings. The
buildings in which licensed materials
were used consist of office space and
laboratories. The Facility is located in a
mixed residential/commercial area.
Within the Facility, use of licensed
materials was confined to Buildings
1,2,6,7 and 15. Notification that all
licensed activities had ceased was
received April 26, 2007.
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Fmt 4703
Sfmt 4703
Need for the Proposed Action
The proposed actions are to approve
the DP so that the Licensee may
complete Facility decommissioning
activities. Completion of the
decommissioning activities will reduce
residual radioactivity at the Facility.
NRC regulations require licensees to
begin timely decommissioning of their
sites, or any separate buildings that
contain residual radioactivity, upon
cessation of licensed activities, in
accordance with 10 CFR 30.36(d) and 10
CFR 40.42(d). The proposed licensing
actions will support such a goal. NRC is
fulfilling its responsibilities under the
Atomic Energy Act to make a decision
on the proposed license amendments for
decommissioning that ensures
protection of the public health and
safety.
Environmental Impacts of the Proposed
Action
The historical review of licensed
activities conducted at the Facility
shows that such activities involved
research and development activities
using sealed and unsealed byproduct
material and source material. The
licensed materials were always stored
and used inside buildings with no
releases.
The NRC staff has reviewed the
Licensee amendment requests for the
Facility and examined the impacts of
these license amendment requests.
Potential impacts include water
resource impact (e.g., water may be used
for dust control), air quality impacts
from dust emissions, temporary local
traffic impacts resulting from
transporting debris, human health
impacts, noise impacts from equipment
operation, scenic quality impacts, and
waste management impacts.
Based on its review, the staff has
determined that no surface water or
ground water impacts are expected from
the decommissioning activities.
Additionally, the staff has determined
that significant air quality, noise, land
use, and off-site radiation exposure
impacts are also not expected. No
significant air quality impacts are
anticipated because of the limited
amount of contamination and the
controls that will be implemented by
the Licensee during decommissioning
activities. In addition, the
environmental impacts associated with
the decommissioning activities are
bounded by impacts evaluated by
NUREG–0586, ‘‘Final Generic
Environmental Impact Statement on the
Decommissioning of Nuclear Facilities,’’
(GEIS). Generic impacts for this type of
decommissioning process were
E:\FR\FM\06AUN1.SGM
06AUN1
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Federal Register / Vol. 74, No. 150 / Thursday, August 6, 2009 / Notices
previously evaluated and described in
the GEIS, which concludes that the
environmental consequences are small.
The risk to human health from the
transportation of all radioactive material
in the U.S. was evaluated in NUREG–
0170, ‘‘Final Environmental Statement
on the Transportation of Radioactive
Materials by Air and Other Modes.’’ The
principal radiological environmental
impact during normal transportation is
direct radiation exposure to nearby
persons from radioactive material in the
package. The average annual individual
dose from all radioactive material
transportation in the U.S. was
calculated to be approximately 0.5
millirem, well below the 10 CFR
20.1301 limit of 100 millirem for a
member of the public. These proposed
actions will not significantly increase
the probability or consequences of
accidents, no changes are being made in
the types of any effluents that may be
released off site, and there is no
significant increase in occupational or
public radiation exposure. Thus, waste
management and transportation impacts
from the decommissioning will not be
significant.
Occupational health was also
considered in the ‘‘Final Environmental
Impact Statement on the Transportation
of Radioactive Material by Air and
Other Modes.’’ Shipment of these
materials would not affect the
assessment of environmental impacts or
the conclusions in the ‘‘Final
Environmental Impact Statement on the
Transportation of Radioactive Material
by Air and Other Modes.’’
The Staff also finds that the proposed
license amendments will meet the
radiological criteria for unrestricted
release as specified in 10 CFR 20.1402.
The Licensee demonstrated this through
the development of derived
concentration guideline limits (DCGLs)
for its Facility. The Licensee conducted
site-specific dose modeling using
parameters specific to the Facility that
adequately bounded the potential dose.
The Licensee will maintain an
appropriate level of radiation protection
staff, procedures, and capabilities, and,
through its Radiation Safety Officer, will
implement an acceptable program to
keep exposure to radioactive materials
as low as reasonably achievable
(ALARA). Work activities are not
anticipated to result in radiation
exposures to the public in excess of ten
percent of the 10 CFR 20.1301 limits.
The NRC also evaluated whether
cumulative environmental impacts
could result from an incremental impact
of the proposed action when added to
other past, present, or reasonably
foreseeable future actions in the area.
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17:04 Aug 05, 2009
Jkt 217001
The proposed NRC approval of the
license amendment requests, when
combined with known effects on
resource areas at the site, including
further site remediation, are not
anticipated to result in any cumulative
impacts at the site.
Environmental Impacts of the
Alternatives to the Proposed Action
The only alternative to the proposed
action of decommissioning the Facility
is the no-action alternative, under
which the staff would leave things as
they are by simply denying the
amendment requests. This no-action
alternative is not feasible because it
conflicts with 10 CFR 30.36(d) and 10
CFR 40.42(d), requiring that
decommissioning of byproduct material
and source material facilities be
completed and approved by the NRC
after licensed activities cease.
Additionally, denying the amendment
requests 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 June 3, 2009.
On July 8, 2009, the New Jersey
Department of Environmental Protection
responded by letter. 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.
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Fmt 4703
Sfmt 4703
39347
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
amendments and supporting
documentation, are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this site,
you can access the NRC’s Agencywide
Documents Access and Management
System (ADAMS), which provides text
and image files of NRC’s public
documents. The documents related to
this action are listed below, along with
their ADAMS accession numbers.
1. NUREG–1757, ‘‘Consolidated
NMSS Decommissioning Guidance;’’
2. Title 10, Code of Federal
Regulations, Part 20, Subpart E,
‘‘Radiological Criteria for License
Termination;’’
3. Title 10, Code of Federal
Regulations, Part 51, ‘‘Environmental
Protection Regulations for Domestic
Licensing and Related Regulatory
Functions;’’ and
4. NUREG–1496, ‘‘Generic
Environmental Impact Statement in
Support of Rulemaking on Radiological
Criteria for License Termination of
NRC–Licensed Nuclear Facilities.’’
5. Submittal Letter dated June 12,
2008 (ML081910071).
6. Decommissioning Plan, Volume 1
(ML081910076).
7. Decommissioning Plan, Volume 2
(ML081910083).
8. Review of Decommissioning Plan
dated April 6, 2009 (ML090960301).
9. Deficiency Response Letter dated
May 21, 2009 (ML091470227).
10. Federal Register Notice of
Consideration (ML083360193).
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.
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06AUN1
39348
Federal Register / Vol. 74, No. 150 / Thursday, August 6, 2009 / Notices
Dated at 475 Allendale Road, King of
Prussia, PA, this 28th day of July 2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division
of Nuclear Materials Safety, Region I.
[FR Doc. E9–18820 Filed 8–5–09; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[NRC–2009–0341]
Nuclear Regulatory Commission’s
Involvement With the Navy’s
Remediation of the Hunters Point
Shipyard Site in San Francisco, CA
jlentini on DSKJ8SOYB1PROD with NOTICES
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of jurisdiction and future
involvement.
SUMMARY: The U.S. Nuclear Regulatory
Commission (NRC) has decided that it
will take a limited involvement
approach to stay informed about the
Navy’s ongoing remediation of the
Hunters Point Shipyard (HPS) site in
San Francisco, California. NRC will rely
on the Comprehensive Environmental
Response, Compensation, and Liability
Act (CERCLA) process and the U.S.
Environmental Protection Agency (EPA)
Region 9 oversight. This notice
discusses NRC’s jurisdiction and future
limited involvement at the HPS site and
how it plans on staying informed about
the Navy’s remediation in the future.
FOR FURTHER INFORMATION CONTACT:
Robert L. Johnson, Division of Waste
Management and Environmental
Protection, Office of Federal and State
Materials and Environmental
Management Programs, Mail Stop T–
8F5, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, telephone: (301) 415–7282; e-mail:
Robert.Johnson2@nrc.gov.
SUPPLEMENTARY INFORMATION: In July
2007 the Navy requested clarification
about NRC‘s jurisdiction and potential
involvement with the Navy’s ongoing
remediation of radioactive material at
the HPS site. In response to the Navy’s
request, NRC reviewed key HPS site
documents, met with the Navy, and
conducted a site visit in October 2007.
NRC also met with representatives from
EPA Region 9, the State of California
agencies involved with the HPS site,
and the City of San Francisco. In
addition to evaluating potential NRC
involvement, these meetings were used
to obtain an understanding of the site,
the Navy’s remediation, and the
oversight roles and issues of the key
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17:04 Aug 05, 2009
Jkt 217001
parties involved with the remediation.
Based on this information, the NRC staff
evaluated NRC’s jurisdiction for the
materials at the HPS site and evaluated
options for NRC involvement. These
options and the staff’s recommendations
were provided to the Commission in
SECY–08–0077. This Commission paper
also gives background about the HPS
and the Navy’s ongoing remediation.
The Commission provided its direction
to the staff on June 26, 2008, in SRM–
SECY–08–0077. The results of the staff’s
evaluation and the Commission’s
decision are summarized in the answers
to the following questions:
1. What is NRC’s regulatory jurisdiction
for the Navy’s remediation of the HPS
site?
Atomic Energy Commission (AEC)
licenses for radioactive material used by
the Navy in both the shipyard and the
Navy Radiological Defense Laboratory
(NRDL) at the HPS site were terminated
in the 1970s after extensive radiological
surveys of the facilities confirmed that
the facilities met the radiological
standards at that time. Therefore, after
termination of the AEC licenses, neither
the NRC nor its predecessor, AEC,
exercised direct regulatory authority
over the residual contamination at the
HPS site. Subsequently, the Navy
conducted radiological surveys and
completed a Historical Radiological
Assessment of the site in 2004. These
studies provided new information about
the suspected and confirmed
radiological contamination for the entire
HPS site. Based on this new
information, the Navy and NRC assume
that any remaining licensable material is
likely commingled with atomic
weapons testing material. Both types of
radioactive material were used at the
NRDL. NRC has jurisdiction for the
licensable material. However, under
Section 91(b) of the AEA, the atomic
weapons testing material is outside of
NRC’s jurisdiction.
2. What is NRC’s future involvement
with the Navy’s ongoing remediation of
the HPS site?
NRC will rely on the ongoing Navy
remediation under the CERCLA process
and EPA regulatory oversight for the
licensable radioactive material assumed
to be present at the HPS site. NRC
would not exercise its regulatory
authority and would not require
compliance with its decommissioning
regulations. NRC would not conduct
any formal regulatory reviews or
participate in the ongoing CERCLA
comment process for the Navy’s
remediation. The NRC staff would have
a limited involvement to stay informed
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Frm 00066
Fmt 4703
Sfmt 4703
about the Navy’s remediation of the
remaining parcels, which is expected to
take about 10 years.
The basis for this approach is that
NRC can reasonably rely on the
CERCLA process and EPA oversight of
this Superfund site because the process
should result in a level of protection of
public health and safety and the
environment that is generally equivalent
to what would be provided if the NRC’s
decommissioning process was used.
NRC believes that this is a reasonable
approach because: (1) The licensable
materials are inextricably commingled
with the atomic weapons testing
material over which NRC has no
jurisdiction; (2) over-laying NRC
requirements and oversight on the
CERCLA process overseen by EPA
provides no clear public health and
safety benefit; (3) dual NRC–EPA
regulation is avoided; (4) remediation
can proceed under CERCLA; and (5)
NRC would be in a position to respond
to stakeholder questions in a timely and
effective manner. NRC considered, but
did not select the option of regulating
the remediation through the Navy’s
Masters Material License with NRC.
This option would have resulted in dual
regulation, unnecessary expenditure of
resources, and no benefit to public
health and safety.
3. How will NRC stay informed about
the Navy’s remediation of the HPS site?
NRC anticipates that it would stay
informed throughout the remediation
process using existing mechanisms,
such as documents received through
standard distributions or that are
available on the Administrative Record
(e.g., records of decision and completion
documents such as the finding of
suitability to transfer). If necessary, NRC
would request access to documents.
Staff would read selected documents
and conduct an annual site visit and
progress meeting with the Navy, EPA,
State agencies, and the City of San
Francisco. The staff would use a riskinformed approach to focus on those
elements of the Navy’s remediation that
are most important to the protection of
public health and safety. The staff
would also focus on those elements that
are currently being planned but not yet
implemented such as formal
establishment of the institutional
controls and engineered controls.
Finally, NRC would also reserve the
option of commenting to EPA if
necessary to justify our continued
reliance on the CERCLA process.
E:\FR\FM\06AUN1.SGM
06AUN1
Agencies
[Federal Register Volume 74, Number 150 (Thursday, August 6, 2009)]
[Notices]
[Pages 39346-39348]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-18820]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[NRC-2008-0639; Docket Nos. 030-05224 and 040-08478]
Notice of Availability of Environmental Assessment and Finding of
No Significant Impact for License Amendments to Byproduct Materials
License No. 29-00170-03 and Source Materials License No. SMB-1260,
Incorporating the Decommissioning Plan for Bell Laboratories Murray
Hill Facility in Murray Hill, NJ
AGENCY: Nuclear Regulatory Commission.
ACTION: Issuance of Environmental Assessment and Finding of No
Significant Impact for License Amendment.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Steve Hammann, Health Physicist,
Commercial and R&D Branch, Division of Nuclear Materials Safety, Region
I, 475 Allendale Road, King of Prussia, Pennsylvania; telephone 610-
337-5399; fax number 610-337-5269; or by e-mail:
stephen.hammann@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC) is considering the
issuance of license amendments to Byproduct Materials License No. 29-
00170-03 and Source Materials License No. SMB-1260. The licenses are
held by Bell Laboratories (the Licensee), for its Murray Hill Facility,
located at 600 Mountain Avenue in Murray Hill, New Jersey (the
Facility). Issuance of the amendments would incorporate the
Decommissioning Plan (DP) into the licenses to allow completion of
decommissioning activities at the site and subsequent release of the
Facility, except one room in the Radiation Lab, for unrestricted use
and the termination of its NRC materials licenses. The room which is
not being released is covered by NRC License No. 29-00170-08. The NRC
has evaluated and approved the Licensee's DP. The findings of this
evaluation are documented in a Safety Evaluation Report which will be
issued along with the amendments. The Licensee requested these actions
in a letter dated June 12, 2008. The Licensee's amendment requests were
noted in the Federal Register on December 8, 2008 (73 FR 74529). This
Federal Register notice also provided an opportunity for a hearing on
these licensing actions. No hearing requests were received. The NRC has
prepared an Environmental Assessment (EA) in support of the proposed
actions 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 actions. The amendments
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 actions would approve the Licensee's June 12, 2008
license amendment requests to incorporate the DP into the licenses,
resulting in decommissioning of the facility and subsequent release of
the Facility, except one room in the Radiation Lab, for unrestricted
use and the termination of its NRC materials licenses. The room which
is not being released is covered by NRC License No. 29-00170-08.
License No. 29-00170-03 was issued on January 25, 1957, pursuant to 10
CFR Part 30, and License No. SMB-1260 was issued on December 2, 1975,
pursuant to 10 CFR Part 40. Both licenses have been amended
periodically since the issue dates. These licenses authorized the
Licensee to use sealed and unsealed byproduct material and source
material for the purpose of conducting research and development
activities on laboratory bench tops and in hoods.
The Facility is situated on 196 acres and encompasses fifteen
buildings. The buildings in which licensed materials were used consist
of office space and laboratories. The Facility is located in a mixed
residential/commercial area. Within the Facility, use of licensed
materials was confined to Buildings 1,2,6,7 and 15. Notification that
all licensed activities had ceased was received April 26, 2007.
Need for the Proposed Action
The proposed actions are to approve the DP so that the Licensee may
complete Facility decommissioning activities. Completion of the
decommissioning activities will reduce residual radioactivity at the
Facility. NRC regulations require licensees to begin timely
decommissioning of their sites, or any separate buildings that contain
residual radioactivity, upon cessation of licensed activities, in
accordance with 10 CFR 30.36(d) and 10 CFR 40.42(d). The proposed
licensing actions will support such a goal. NRC is fulfilling its
responsibilities under the Atomic Energy Act to make a decision on the
proposed license amendments for decommissioning that ensures protection
of the public health and safety.
Environmental Impacts of the Proposed Action
The historical review of licensed activities conducted at the
Facility shows that such activities involved research and development
activities using sealed and unsealed byproduct material and source
material. The licensed materials were always stored and used inside
buildings with no releases.
The NRC staff has reviewed the Licensee amendment requests for the
Facility and examined the impacts of these license amendment requests.
Potential impacts include water resource impact (e.g., water may be
used for dust control), air quality impacts from dust emissions,
temporary local traffic impacts resulting from transporting debris,
human health impacts, noise impacts from equipment operation, scenic
quality impacts, and waste management impacts.
Based on its review, the staff has determined that no surface water
or ground water impacts are expected from the decommissioning
activities. Additionally, the staff has determined that significant air
quality, noise, land use, and off-site radiation exposure impacts are
also not expected. No significant air quality impacts are anticipated
because of the limited amount of contamination and the controls that
will be implemented by the Licensee during decommissioning activities.
In addition, the environmental impacts associated with the
decommissioning activities are bounded by impacts evaluated by NUREG-
0586, ``Final Generic Environmental Impact Statement on the
Decommissioning of Nuclear Facilities,'' (GEIS). Generic impacts for
this type of decommissioning process were
[[Page 39347]]
previously evaluated and described in the GEIS, which concludes that
the environmental consequences are small. The risk to human health from
the transportation of all radioactive material in the U.S. was
evaluated in NUREG-0170, ``Final Environmental Statement on the
Transportation of Radioactive Materials by Air and Other Modes.'' The
principal radiological environmental impact during normal
transportation is direct radiation exposure to nearby persons from
radioactive material in the package. The average annual individual dose
from all radioactive material transportation in the U.S. was calculated
to be approximately 0.5 millirem, well below the 10 CFR 20.1301 limit
of 100 millirem for a member of the public. These proposed actions will
not significantly increase the probability or consequences of
accidents, no changes are being made in the types of any effluents that
may be released off site, and there is no significant increase in
occupational or public radiation exposure. Thus, waste management and
transportation impacts from the decommissioning will not be
significant.
Occupational health was also considered in the ``Final
Environmental Impact Statement on the Transportation of Radioactive
Material by Air and Other Modes.'' Shipment of these materials would
not affect the assessment of environmental impacts or the conclusions
in the ``Final Environmental Impact Statement on the Transportation of
Radioactive Material by Air and Other Modes.''
The Staff also finds that the proposed license amendments will meet
the radiological criteria for unrestricted release as specified in 10
CFR 20.1402. The Licensee demonstrated this through the development of
derived concentration guideline limits (DCGLs) for its Facility. The
Licensee conducted site-specific dose modeling using parameters
specific to the Facility that adequately bounded the potential dose.
The Licensee will maintain an appropriate level of radiation
protection staff, procedures, and capabilities, and, through its
Radiation Safety Officer, will implement an acceptable program to keep
exposure to radioactive materials as low as reasonably achievable
(ALARA). Work activities are not anticipated to result in radiation
exposures to the public in excess of ten percent of the 10 CFR 20.1301
limits.
The NRC also evaluated whether cumulative environmental impacts
could result from an incremental impact of the proposed action when
added to other past, present, or reasonably foreseeable future actions
in the area. The proposed NRC approval of the license amendment
requests, when combined with known effects on resource areas at the
site, including further site remediation, are not anticipated to result
in any cumulative impacts at the site.
Environmental Impacts of the Alternatives to the Proposed Action
The only alternative to the proposed action of decommissioning the
Facility is the no-action alternative, under which the staff would
leave things as they are by simply denying the amendment requests. This
no-action alternative is not feasible because it conflicts with 10 CFR
30.36(d) and 10 CFR 40.42(d), requiring that decommissioning of
byproduct material and source material facilities be completed and
approved by the NRC after licensed activities cease. Additionally,
denying the amendment requests 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 June 3,
2009. On July 8, 2009, the New Jersey Department of Environmental
Protection responded by letter. 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 amendments and supporting documentation, are available
electronically at the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this site, you can access the
NRC's Agencywide Documents Access and Management System (ADAMS), which
provides text and image files of NRC's public documents. The documents
related to this action are listed below, along with their ADAMS
accession numbers.
1. NUREG-1757, ``Consolidated NMSS Decommissioning Guidance;''
2. Title 10, Code of Federal Regulations, Part 20, Subpart E,
``Radiological Criteria for License Termination;''
3. Title 10, Code of Federal Regulations, Part 51, ``Environmental
Protection Regulations for Domestic Licensing and Related Regulatory
Functions;'' and
4. NUREG-1496, ``Generic Environmental Impact Statement in Support
of Rulemaking on Radiological Criteria for License Termination of NRC-
Licensed Nuclear Facilities.''
5. Submittal Letter dated June 12, 2008 (ML081910071).
6. Decommissioning Plan, Volume 1 (ML081910076).
7. Decommissioning Plan, Volume 2 (ML081910083).
8. Review of Decommissioning Plan dated April 6, 2009
(ML090960301).
9. Deficiency Response Letter dated May 21, 2009 (ML091470227).
10. Federal Register Notice of Consideration (ML083360193).
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.
[[Page 39348]]
Dated at 475 Allendale Road, King of Prussia, PA, this 28th day
of July 2009.
For the Nuclear Regulatory Commission.
James P. Dwyer,
Chief, Commercial and R&D Branch, Division of Nuclear Materials Safety,
Region I.
[FR Doc. E9-18820 Filed 8-5-09; 8:45 am]
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