[Federal Register Volume 77, Number 140 (Friday, July 20, 2012)]
[Notices]
[Pages 42771-42774]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2012-17733]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 50-264; NRC-2012-0026]
License Renewal for the Dow Chemical TRIGA Research Reactor
AGENCY: Nuclear Regulatory Commission.
ACTION: Environmental assessment and finding of no significant impact;
availability.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: Geoffrey A. Wertz, Project Manager,
Research and Test Reactor Licensing Branch, Division of Policy and
Rulemaking, Office of Nuclear Reactor Regulation, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001; telephone: 301-415-
0893; email: [email protected].
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is
considering issuance of a renewed Facility Operating License No. R-108,
to be held by Dow Chemical (Dow, or the licensee), which would
authorize continued operation of the Dow Training, Research, Isotope
production, General Atomics (TRIGA) Research Reactor, located in
Midland County, MI. Therefore, as required by Title 10 of the Code of
Federal Regulations (10 CFR) 51.21, the NRC is issuing this
Environmental Assessment and Finding of No Significant Impact. The
renewed license will be issued following the publication of this
document.
II. EA Summary
Identification of the Proposed Action: The proposed action would
renew Facility Operating License No. R-108 for a period of 20 years
from the date of issuance of the renewed license. The proposed action
is in accordance with the licensee's application dated April 1, 2009,
as supplemented on September 24, 2010; January 12, February 11, April
20, May 12, May 27, August 12, August 31, October 12, November 10, and
December 6, 2011; and January 13, January 20, February 7, and June 11,
2012. In accordance with 10 CFR 2.109, the existing license remains in
effect until the NRC takes final action on the renewal application.
Need for the Proposed Action: The proposed action is needed to
allow the continued operation of the Dow TRIGA Research Reactor to
routinely provide opportunities to conduct neutron activation analysis,
isotope production, neutron radiography, and irradiation studies for a
period of 20 years.
Environmental Impacts of the Proposed Action: The NRC completed its
safety evaluation of the proposed action to issue a renewed Facility
Operating License No. R-108 to allow continued operation of the Dow
TRIGA Research Reactor for an additional 20 years and concluded there
is reasonable assurance that the Dow TRIGA Research Reactor will
continue to operate safely for the additional period of time. The
details of the NRC staff's safety evaluation will be provided with the
renewed license that will be issued as part of the letter to the
licensee approving its license renewal application. This document
contains the environmental assessment of the proposed action.
The Dow TRIGA Research Reactor is located on the Michigan Division
of the Dow Chemical Company in Midland, MI and is a part of the
Analytical Sciences Laboratory. The reactor is housed in a laboratory
building constructed of concrete panel, concrete block walls, and steel
frame. The reactor site comprises of the reactor building. Adjacent to
the site are research buildings to the east and other industrial
buildings in the outlying area. The nearest residence is located
approximately 480 meters (530 yards) from the site boundary.
The Dow TRIGA Research Reactor is a pool-type, light water
moderated and cooled research reactor licensed to operate at a steady-
state power level of 300 kilowatt (kW) thermal power. The fuel is
located at the bottom of an aluminum lined concrete pool with a volume
of approximately 19,000 liters (5,000 gallons) and a depth of 6.5
meters (21.5 feet). The reactor is fueled with standard low-enriched
uranium TRIGA fuel. A detailed description of the reactor can be found
in the Safety Analysis Report (SAR) for the Dow TRIGA Research Reactor
dated April 1, 2009. There were two major modifications to the Facility
Operating License No. R-108 since renewal of the license on May 8,
1989. License Amendment No. 6 dated December 13, 1990, approved
installation of a microprocessor based instrument and control system. A
heat exchanger upgrade was completed in 2005, and a review in
accordance with 10 CFR 50.59 was completed by the licensee prior to
return to operation.
The licensee has not requested a change to the facility design or
operating conditions as part of the renewal request. No changes are
being made in the types or quantities of effluents that may be released
off site. The licensee has systems in place to control the release of
radiological effluents and implements a radiation protection program to
monitor personnel exposures and releases of radioactive effluents. As
discussed in the NRC staff's safety evaluation, the systems and
radiation protection program are appropriate for the types and
quantities of effluents expected to be generated by continued operation
of the reactor. There would be no increase in routine occupational or
public radiation exposure as a result of license renewal. As discussed
in the NRC staff's safety evaluation, the proposed action will not
significantly increase the probability or consequences of accidents.
Therefore, the NRC staff finds that license renewal would not
change the environmental impact of facility operation. The NRC staff
evaluated information contained in the licensee's application and data
reported to the NRC by the licensee for the last six years of operation
to determine the projected radiological impact of the facility on the
environment during the period of the renewed license. The NRC staff
finds that releases of radioactive material and personnel exposures
were all well within applicable regulatory limits. Based on its
evaluation, the NRC staff concludes that continued operation of the
reactor would not have a significant environmental impact.
A. Radiological Impact
Environmental Effects of Reactor Operations
Gaseous radioactive effluents are discharged by the facility
exhaust system via an exhaust vent located 8 feet above ground on the
side of the reactor room, at a volumetric flow rate of approximately 48
cubic meters per
[[Page 42772]]
minute (1700 cubic feet per minute). A fume hood in the laboratory
adjacent to the reactor room used for sample preparation exhausts
through a stack on top of the reactor building. Other release pathways
do exist; however, they are normally secured during reactor operation
and have insignificant volumetric flow rates compared to the facility
exhaust system. The only significant nuclide found in the gaseous
effluent stream is Argon-41. The licensee performed calculations to
estimate the production level of Argon-41 associated with operation of
the reactor at high power. The licensee's calculations indicated that
annual Argon-41 release would result in an offsite concentration of
9.8E-10 microcuries per milliliter ([mu]Ci/ml), which is below the
limit of 1.0E-8 [mu]Ci/ml specified in 10 CFR Part 20, Appendix B for
air effluent releases. The NRC staff reviewed the licensee's
calculation and found it to be acceptable. The bounding calculation of
total gaseous radioactive releases is less than two percent of the air
effluent concentration limits set by 10 CFR Part 20, Appendix B. The
potential annual radiation dose to a member of the general public
resulting from this concentration is approximately 0.00056
milliSieverts (mSv) (0.056 millirems (mrem)), and this demonstrates
compliance with the dose limit of 1 mSv (100 mrem) set by 10 CFR
20.1301. Additionally, this potential radiation dose demonstrates
compliance with the air emissions dose constraint of 0.1 mSv (10 mrem)
specified in 10 CFR 20.1101(d).
The licensee disposes of liquid radioactive wastes by solidifying
liquid waste. The NRC staff's review of Dow TRIGA Research Reactor
annual reports covering the last 6 years indicated that the licensee
reported no routine releases of liquid radioactive waste by any of the
disposal methods.
Solid low-level radioactive waste generated at the Dow TRIGA
Research Reactor is disposed under the guidance of the Radiation Safety
Committee and the site Radiation Safety Officer using the Dow Radiation
Protection Manual. The bulk of the waste consists of samples, sample
vials, gloves, and paper towels. The licensee disposes of the waste by
decay in storage or shipment to a low level waste broker in accordance
with all applicable regulations for transportation of radioactive
materials. The licensee stated that no spent nuclear fuel has been
shipped from the site to date. To comply with the Nuclear Waste Policy
Act of 1982, Dow Chemical Company has entered into a contract with the
U.S. Department of Energy (DOE) that provides that DOE retains title to
the fuel utilized at the Dow TRIGA Research Reactor and that DOE is
obligated to take the fuel from the site for final disposition.
Chapter K of the Dow TRIGA Research Reactor SAR stated that
personnel exposures are well within the limits set by 10 CFR 20.1201,
and are as low as is reasonably achievable (ALARA). The Radiation
Protection Program tracks personnel exposures, which are usually less
than 0.01 mSv (10 mrem) per year. Personnel dosimeters mounted on the
interior walls of the reactor room provide a quarterly measurement of
total radiation exposures at those locations. These dosimeters
typically measure annual doses of less than 0.1 mSv (100 mrem) in the
reactor room. No changes in reactor operation that would lead to an
increase in occupational dose are expected as a result of the proposed
action.
Based on the NRC staff's review of the past 6 years of data from
the Dow TRIGA research reactor annual reports, the NRC staff concluded
that operation of the Dow TRIGA Research Reactor does not have any
significant radiological impact on the surrounding environment. No
changes in reactor operation that would affect off-site radiation
levels are expected as a result of license renewal.
Environmental Effects of Accidents
Accident scenarios are discussed in Chapter M of the Dow TRIGA
Research Reactor SAR. The maximum hypothetical accident (MHA) is the
uncontrolled release of the gaseous fission products contained in the
gap between the fuel and the fuel cladding in one fuel element to the
reactor building and into the environment. The licensee conservatively
calculated doses to facility personnel and the maximum potential dose
to a member of the public in the event of the MHA. The NRC staff
performed independent calculations to verify that the doses provided by
the licensee represented conservative estimates for the MHA. The
results are provided in the DTRR License Renewal Safety Evaluation
Report. The NRC staff concluded that the maximum doses resulting from
this hypothetical accident would be well below the limits in 10 CFR
Part 20 of 50 mSv (5000 mrem) for occupational workers, and 1 mSv (100
mrem) for members of the public. The proposed action will not increase
the probability or consequences of accidents.
B. Non-Radiological Impacts
The Dow TRIGA Research Reactor core is cooled by a light water
primary system consisting of the reactor pool, a heat removal system,
and a processing system. Cooling occurs by natural convection, with the
heated coolant rising out of the core and into the bulk pool water. The
large heat sink provided by the volume of primary coolant allows
several hours of full-power operation without any secondary cooling.
The heat removal system transfers heat to the secondary system via a
100 kW-heat exchanger and a 1 megawatt (MW) heat exchanger. The
secondary system normally uses a 1 MW, closed loop system, through a
chiller which discharges the heat directly to atmosphere. The secondary
system may be cooled by a 100 kW heat exchanger. The heat is
transferred to potable water which is discharged to a sewer system.
During operation, the secondary system is maintained at a higher
pressure than the primary system to minimize the likelihood of primary
system contamination entering the secondary system and ultimately the
environment.
Based on the information described above, the NRC staff finds that
release of thermal effluents from the DOW TRIGA Research Reactor will
not have a significant effect on the environment. The licensee complies
with the appropriate Michigan Department of Environmental Protection
permit for secondary water discharge, and no violations of the permit
have occurred. Given that the proposed action does not involve any
change in the operation of the reactor, the NRC staff concludes that
the proposed action will not have a significant impact on the local
water supply.
National Environmental Policy Act (NEPA) Considerations
The NRC has responsibilities that are derived from NEPA and from
other environmental laws, which include the Endangered Species Act
(ESA), Coastal Zone Management Act (CZMA), National Historic
Preservation Act (NHPA), Fish and Wildlife Coordination Act (FWCA), and
Executive Order 12898 Environmental Justice. The following presents a
brief discussion of impacts associated with these laws and other
requirements.
A. Endangered Species Act
Federally- or State-listed protected species have not been found in
the immediate vicinity of the Dow TRIGA Research Reactor, and effluents
and emissions from the reactor have had no impact on critical habitat.
Therefore, no
[[Page 42773]]
effects on the aquatic or terrestrial habitat in the vicinity of the
Dow TRIGA Research Reactor or to threatened, endangered, or protected
species under the Endangered Species Act would be expected. The NRC
staff consulted the State of Michigan, Department of Natural Resources
and Environment who stated, ``The project should have no impact on rare
or unique natural features at the locations specified above if it
proceeds according to the plans provided.''
B. Coastal Zone Management Act
The Dow TRIGA Research Reactor is not located within any managed
coastal zones, nor would the effluents and emissions from the Dow TRIGA
Research Reactor impact any managed coastal zones.
C. National Historic Preservation Act
The NHPA requires Federal agencies to consider the effects of their
undertakings on historic properties. The National Register of Historic
Places (NRHP) lists the closest historic property as the Midland County
Courthouse. The Midland County Courthouse is located at 301 West Main
Street, Midland, MI, and is approximately 2.1 km (1.3 miles) northwest
of the Dow TRIGA Research Reactor. Given the distance between the
facility and the Midland County Courthouse, continued operation of the
Dow TRIGA Research Reactor will not impact any historical sites. A
Section 106 Review was submitted to the State Historic Preservation
Office regarding this activity. The State Historic Preservation Office
concurred that this activity did not affect historic properties.
D. Fish and Wildlife Coordination Act
The licensee is not planning any water resource development
projects, including any modifications involving impounding a body of
water, damming, diverting a stream or river, deepening a channel,
irrigation, or altering a body of water for navigation or drainage.
E. Executive Order 12898--Environmental Justice
The environmental justice impact analysis evaluates the potential
for disproportionately high and adverse human health and environmental
effects on minority and low-income populations that could result from
the license renewal and the continued operation of the Dow TRIGA
Research Reactor. Such effects may include human health, biological,
cultural, economic, or social impacts. Minority and low-income
populations are subsets of the general public residing around the Dow
TRIGA Research Reactor and all are exposed to the same health and
environmental effects generated from activities at the Dow TRIGA
Research Reactor.
Minority Populations in the Vicinity of the Dow TRIGA Research
Reactor--According to 2010 census data, 7.2 percent of the total
population (approximately 5,779 individuals) residing within a 10-mile
radius of the Dow TRIGA Research Reactor identified themselves as
minority individuals. The largest minority groups were Hispanic or
Latino (of any race) (1,848 or 2.3 percent) followed by Asian (1,582 or
2 percent). According to U.S. Census Bureau 2010 estimates, about 7
percent of the Midland County population identified themselves as
minorities, with persons of Hispanic or Latino origin (of any race)
comprising the largest minority group (2.1 percent), followed by Asian
(2.1 percent) and Black or African American (1.4 percent).
Low-income Populations in the Vicinity of the Dow TRIGA Research
Reactor--According to 2010 Census data, an average of 10.2 percent of
families and 14.5 percent of individuals residing within counties in a
10-mile radius of the reactor (Midland, Bay, and Saginaw Counties),
were identified as living below the Federal poverty threshold in 2010.
The 2010 Federal poverty threshold was $22,314 for a family of four.
According to American Community Survey census data estimates for
2010, the median household income for Michigan was $45,413, while 12.1
percent of families and 16.8 percent of the state population were
determined to be living below the Federal poverty threshold. Midland
County had a higher median household income average ($60,543) and a
lower percent of families (7.1 percent) and individuals (10.4 percent)
living below the poverty level, respectively.
Impact Analysis--Potential impacts to minority and low-income
populations would mostly consist of radiological effects, however
radiation doses from continued operations associated with the license
renewal are expected to continue at current levels, and would be well
below regulatory limits.
Based on information described above and the analysis of human
health and environmental impacts presented in this environmental
assessment, the proposed license renewal would not have
disproportionately high and adverse human health and environmental
effects on minority and low-income populations residing in the vicinity
of the Dow TRIGA Research Reactor.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to license renewal, the NRC staff considered
denial of the proposed action. If the NRC denied the application for
license renewal, facility operations would end and decommissioning
would be required. The NRC staff notes that, even with a renewed
license, the Dow TRIGA Research Reactor will eventually require
decommissioning, at which time the environmental effects of
decommissioning will occur. Decommissioning will be conducted in
accordance with an NRC-approved decommissioning plan which will require
a separate environmental review under 10 CFR 51.21. Cessation of
facility operations would reduce radioactive effluents. However, as
previously discussed in this environmental assessment, radioactive
effluents resulting from facility operations constitute only a small
fraction of the applicable regulatory limits. Therefore, the
environmental impacts of license renewal and denial of the application
for license renewal are similar. In addition, denial of the application
for license renewal would cause the loss of the benefits of teaching,
research, and services provided by facility operation.
Alternative Use of Resources
The proposed action does not involve the use of any different
resources or significant quantities of resources beyond those
previously considered in the issuance of License Amendment No. 6 to
Facility Operating License No. R-108 for the Dow TRIGA Research Reactor
dated December 13, 1990, which amended the Facility Operating License
No. R-108 and technical specifications to allow the installation of a
microprocessor based instrumentation and control system.
Agencies and Persons Consulted
On February 2, 2102, the NRC provided a draft of this Environmental
Assessment to the Resource Management Division of the Michigan
Department of Environmental Quality for review. On March 5, 2012, the
Resource Management Division of the Michigan Department of
Environmental Quality responded by electronic mail agreeing with the
conclusions of the draft EA, and otherwise had no comments.
The State of Michigan, Department of Natural Resources and
Environment was consulted via its Web site on the proposed activity. On
May 7, 2010, the Department of Natural Resources and
[[Page 42774]]
Environment concurred that there was no effect on endangered species,
and otherwise had no comments.
On December 12, 2010, the NRC staff also provided information
regarding the proposed activity to the State Historic Preservation
Office for a Section 106 Review. On March 4, 2011, the State Historic
Preservation Office concurred that the proposed action has no effect on
historic properties.
Finding of No Significant Impact
The NRC staff performed an environmental assessment of the proposed
action. The NRC staff concludes that the proposed action will not have
a significant effect on the quality of the human environment.
Accordingly, the NRC staff has determined not to prepare an
environmental impact statement for the proposed action.
III. Further Information
Documents related to this proposed action, including the
application for license renewal and supporting documentation, are
available electronically at the NRC's Library at http://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 ADAMS
accession numbers for the documents related to this document are: The
application and its supplements, April 1, 2009 (ADAMS Accession No.
ML092150443) and September 24, 2010 (ADAMS Accession No. ML102720859);
January 12 (ADAMS Accession No. ML110130501), February 11 (ADAMS
Accession No. ML110490391), April 20 (ADAMS Accession No. ML113460120),
May 12, (ADAMS Accession No. ML11136A229), May 27 (ADAMS Accession No.
ML112150327), August 12 (ADAMS Accession Nos. ML11228A116), August 31
(ADAMS Accession No. ML11249A043), October 12 (ADAMS Accession No.
ML112930035), November 10 (ADAMS Accession No. ML113410168), and
December 6, 2011 (ADAMS Accession No. ML113460038); and January 13
(ADAMS Accession No. ML 12019A007), January 20, (ADAMS Accession No.
ML12025A089 and ML12026A152), February 7, 2012 (ADAMS Accession No.
ML12040A128), and June 11, 2012 (ADAMS Accession No. ML12164A784).
Letters and electronic mail from the State consultations, May 7, 2010
(ADAMS Accession No. ML101340317), March 4, 2011 (ADAMS Accession No.
ML110740100), and March 5, 2012 (ADAMS Accession No. ML120730278). If
you do not have access to ADAMS or if there are problems in accessing
the documents located in ADAMS, contact the NRC's Public Document Room
(PDR) Reference staff at 1-800-397-4209, or 301-415-4737 or by email to
[email protected]. These documents may also be viewed electronically on the
public computers located at the NRC's PDR, Room No. O1 F21 (first
floor), One White Flint North, 11555 Rockville Pike, Rockville,
Maryland 20852. The PDR reproduction contractor will copy documents for
a fee.
Dated at Rockville, Maryland, this 10th day of July, 2012.
For the Nuclear Regulatory Commission.
Jessie F. Quichocho,
Chief, Research and Test Reactors Licensing Branch, Division of Policy
and Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. 2012-17733 Filed 7-19-12; 8:45 am]
BILLING CODE 7590-01-P