United States Department of the Interior, United States Geological Survey TRIGA Research Reactor, 38739-38745 [2016-14078]

Agencies

• NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 81, Number 114 (Tuesday, June 14, 2016)]
[Notices]
[Pages 38739-38745]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2016-14078]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-274; NRC-2015-0284]


United States Department of the Interior, United States 
Geological Survey TRIGA Research Reactor

AGENCY: Nuclear Regulatory Commission.

ACTION: Environmental assessment and finding of no significant impact; 
issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is considering 
renewal of Facility Operating License No. R-113, held by the United 
States Geological Survey (USGS or the licensee), for the continued 
operation of its USGS Training, Research, Isotope Production, General 
Atomics (TRIGA) research reactor (GSTR or the reactor). The NRC is 
issuing an environmental assessment (EA) and finding of no significant 
impact (FONSI) associated with the renewal of the license.

DATES: The EA and FONSI are available as of June 14, 2016.

ADDRESSES: Please refer to Docket ID NRC-2015-0284 when contacting the 
NRC about the availability of information regarding this document. You 
may obtain publicly-available information related to this document 
using any of the following methods:
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2015-0284. Address 
questions about NRC dockets to Carol

[[Page 38740]]

Gallagher; telephone: 301-415-3463; email: Carol.Gallagher@nrc.gov. For 
technical questions, contact the individual listed in the FOR FURTHER 
INFORMATION CONTACT section of this document.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may obtain publicly-available documents online in the 
ADAMS Public Documents collection at https://www.nrc.gov/reading-rm/adams.html. To begin the search, select ``ADAMS Public Documents'' and 
then select ``Begin Web-based ADAMS Search.'' For problems with ADAMS, 
please contact the NRC's Public Document Room (PDR) reference staff at 
1-800-397-4209, 301-415-4737, or by email to pdr.resource@nrc.gov. For 
the convenience of the reader, the ADAMS accession numbers are provided 
in a table in the ``Availability of Documents'' section of this 
document.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Geoffrey A. Wertz, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001; telephone: 301-415-0893; email: Geoffrey.Wertz@nrc.gov.

SUPPLEMENTARY INFORMATION: 

I. Introduction

    The NRC is considering renewal of Facility Operating License No. R-
113, held by the USGS, which would authorize continued operation of its 
reactor, located in the Denver Federal Center, Lakewood, Colorado. 
Therefore, as required by section 51.21 of title 10 of the Code of 
Federal Regulations (10 CFR), ``Criteria for and identification of 
licensing and regulatory actions requiring environmental assessments,'' 
the NRC performed an EA. Based on the results of the EA that follows, 
the NRC has determined not to prepare an environmental impact statement 
for the renewed license, and is issuing a FONSI.

II. Environmental Assessment

Identification of the Proposed Action

    The proposed action would renew Facility Operating License No. R-
113 for an additional 20 years from the date of issuance of the renewal 
license. The proposed action is in accordance with the licensee's 
application dated January 5, 2009, as supplemented by letters dated 
November 24, 2010; February 11, March 28, May 12, June 29, July 27, 
August 30, September 26, October 31, and November 30, 2011; January 3, 
January 27 (two letters), March 28, April 27, May 18, May 31, June 29, 
July 31, August 30, and November 16, 2012; February 8, May 17, and 
October 31, 2013; November 3, and November 24, 2014; September 8, 2015; 
and January 22, and April 1, 2016, (the renewal application). 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 GSTR to routinely provide teaching, research, and services to 
numerous institutions for a period of 20 years.

Environmental Impacts of the Proposed Action

    The NRC has completed its safety evaluation (SE) of the proposed 
action to issue a renewed Facility Operating License No. R-113 to allow 
continued operation of the GSTR for a period of 20 years and concludes 
there is reasonable assurance that the GSTR will continue to operate 
safely for the additional period of time. The details of the NRC 
staff's SE 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 EA of the proposed 
action.
    The GSTR is located within the Nuclear Science Building, Building 
15, located on the Denver Federal Center, northwest of downtown 
Lakewood, Colorado, approximately 4 miles (6.4 kilometers) south of 
Interstate 70 and 10 miles (16 kilometers) west of downtown Denver, 
Colorado. The initial construction of Building 15 was completed in 1966 
and the initial operating license was issued in February 1969. There 
are no permanent residences on the Denver Federal Center property, and 
the nearest residence is 2,100 feet (640 meters) from the GSTR.
    The GSTR is a pool-type, light-water cooled, graphite-reflected 
research reactor licensed to operate at a maximum steady-state power 
level of 1.0 megawatt thermal power (MW) and has the capability to 
pulse to a peak power of approximately 1,600 MW. The fuel is located at 
the bottom of the inner aluminum tank with a diameter of approximately 
7.5 feet (2.3 meters) and a depth of 25 feet (7.6 meters). The reactor 
is fueled with uranium-zirconium hydride TRIGA fuel elements with a 
uranium-235 enrichment of less than 20 percent. A detailed description 
of the reactor can be found in the GSTR Safety Analysis Report (SAR). 
There have been no major modifications to the GSTR or the Facility 
Operating License since issuing the operating license in February 1966.
A. Radiological Impacts

Environmental Effects of Reactor Operations

    Gaseous radioactive effluents are discharged by the ventilation 
exhaust located on the roof of the building, at a volumetric flow rate 
of approximately 1000 cubic feet per minute (cfm) (28.3 cubic meters 
per minute). The reactor bay is maintained at a negative pressure 
relative to the outside environment, which helps ensure that any 
release pathways are through the ventilation exhaust that provides an 
elevated release point for dispersion of the effluent. This release 
pathway is monitored by GSTR staff. The only significant nuclide found 
in the gaseous effluent stream is Argon-41. The licensee has a current 
technical specification (TS) which limits the release of Argon-41 to an 
average annual concentration of 4.8E-6 microcuries/milliliter 
([micro]Ci/ml). Argon-41 is released from the GSTR through a roof stack 
at an elevation of 21 feet (6.4 meters) above grade as specified in the 
GSTR TSs. The concentration of Argon-41 will be reduced by dispersion 
and dilution before it reaches the unrestricted area. The purpose of 
the TS is to help ensure that doses from Argon-41 released from the 
facility are within NRC regulatory requirements. Assuming continuous 
operation of the GSTR in order to continuously produce and release 
Argon-41 at the TS limit of 4.8E-6 [micro]Ci/ml, and a volumetric flow 
rate of 1,000 cfm from the exhaust stack, the total release of Argon-41 
to the environment would be approximately 71.44 curies in a year.
    The licensee performed calculations, assuming a continuous release 
of Argon-41 at the TS limit (4.8E-6 [micro]Ci/ml), and determined that 
the potential radiation dose to a member of the public, who could be 
continuously exposed for an entire year at the nearest publicly-
available location, 1,558 feet (475 meters) from the GSTR, was 
approximately 0.3 millirem (mrem) (0.003 milliSieverts (mSv)) per year. 
The licensee also performed calculations for various locations within 
the Denver Federal Center, using occupancy factors to account for the 
duration that persons could be exposed. The maximum exposure was at the 
Building 15 south door. Using a conservative occupancy factor of 5 
percent (1.75 hours per work day or 437 hours per year) to account for 
the time that an individual may be at

[[Page 38741]]

the door, the maximum radiation exposure was 6.75 mrem (0.0675 mSv). 
Using an occupancy factor of 22.8 percent (40 hours per week for 50 
weeks per year), the licensee calculated that the annual dose to a 
person at the entrance to the nearest building (Building 21--161 feet 
(49 meters) away) was 2.37 mrem (0.024mSv).
    A review of the licensee's annual reports for the previous 5 years 
of operation shows that the maximum annual release of Argon-41 for the 
five year time period was approximately 13 curies in 2013. Using 
reactor operation as provided in the 2013 annual report, which was 
1,118 hours, the approximate average concentration released from the 
roof stack during reactor operation was calculated to be 6.8E-12 curies 
per milliliter (Ci/ml), which is well below the limit of 1.0E-8 Ci/ml 
as specified in 10 CFR part 20, appendix B for air effluent releases.
    The licensee also considered the radiological effect of Nitrogen-
16, which is produced from neutron activation of Oxygen-16 in the 
reactor pool coolant water. Nitrogen-16 decays with a very short half-
life of 7 seconds, and given that the GSTR has a nitrogen diffuser, 
which provides a delay in the time it takes for the Nitrogen-16 to 
transit from the reactor core to the pool surface, most of the 
Nitrogen-16 has been removed through decay prior to reaching the pool 
surface. Other radioactive gaseous effluents released were reported to 
the NRC in the licensees' annual reports and were approximately 5 
percent or less of the air effluent concentration limits set by 10 CFR 
part 20, appendix B. The NRC staff reviewed the radiological dose 
calculations provided by the licensee, the assumptions used, and the 
results of several years effluent releases from the licensee's annual 
reports, as well as toured the facility, and finds that the results of 
the licensee's dose estimates to be reasonable.
    Since the potential radiation dose resulting from the effluent 
release from the normal operation of the GSTR to a person in the 
unrestricted area outside the Denver Federal Center, is less than 1 
mrem (0.01 mSv), and to the maximum exposed person on the Denver 
Federal Center is less than 7 mrem (0.07 mSv), the licensee 
demonstrates compliance with the dose limit of 100 mrem (1 mSv) set by 
10 CFR 20.1301. Additionally, this potential radiation dose also 
demonstrates compliance with the air emissions dose constraint of 10 
mrem (0.1 mSv) specified in 10 CFR 20.1101(d).
    The licensee does not routinely dispose of liquid radioactive 
wastes. Normal operations of the GSTR do not generate liquid 
radioactive waste, and the licensee's policy is not to dispose of any 
liquid radioactive waste directly to the environment or to the sanitary 
sewer. The occasional liquid radioactive waste generated at the GSTR 
includes irradiated samples, liquid standards, decontamination waste 
water, and reactor tank pool water. Primary coolant water is purified 
by a mixed-bed demineralizer which maintains the conductivity levels 
low in order to minimize the corrosion potential of the reactor 
components. Radioactive liquid generated during the resin exchange 
process or minor amounts collected in the reactor tank or from other 
uses are evaporated and disposed of as solid radioactive waste. A 
review of the GSTR annual reports submitted to the NRC for the past 5 
years, through 2014, indicated that the licensee reported no routine 
releases of liquid radioactive waste.
    The licensee's health physics staff oversees the handling of solid 
low-level radioactive waste generated at the GSTR. The bulk of the 
waste consists of ion exchange resin, irradiated samples, lab-ware, and 
anti-contamination clothing. The resins used in the demineralizer are 
replaced every 2 to 3 years, and any radioactive material captured in 
the resins are disposed with the resins as solid radioactive waste. The 
resin is aggregated for disposal as solid radioactive waste, until a 
quantity sufficient for disposal can be collected, which allows 
significant radioactive decay to further reduce the amount of solid 
radioactive waste.
    The licensee disposes of the waste by transferring it to a low-
level waste broker in accordance with all applicable regulations for 
transportation of radioactive materials.
    To comply with the Nuclear Waste Policy Act of 1982, the USGS 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 GSTR and 
that DOE is obligated to take the fuel from the site for final 
disposition.
    As described in Chapter 11 of the GSTR SAR, personnel exposures are 
well within the limits set by 10 CFR 20.1201, ``Occupational dose 
limits for adults,'' and are as low as is reasonably achievable. The 
licensee health physics staff monitors personnel exposures, which are 
documented in the licensee's annual reports, and which are consistently 
less than 10 percent of the occupational limit of 5,000 mrem (50 mSv) 
per year. The TSs require a continuous air monitor and an area 
radiation monitor to be operable during reactor operation, in order to 
provide an indication of any change in the radiation levels. The NRC 
staff reviewed the operating experience from the GSTR, which is 
documented in both the licensee's annual reports and the NRC staff's 
inspection reports, and found that radiation exposures to personnel 
working in the GSTR from both direct and airborne radiation during 
normal operation, were within the limits of 10 CFR 20.1201. No changes 
in reactor operation that would lead to an increase in occupational 
dose are expected as a result of the proposed action.
    The licensee conducts an environmental monitoring program to record 
and track the radiological impact of GSTR operation on the surrounding 
unrestricted area. The program consists of quarterly exposure 
measurements at six locations. Biennially, soil and water samples are 
taken around the facility and analyzed for contamination. The licensee 
health physics staff administers the program and maintains the 
appropriate records. The NRC staff review of the environmental survey 
program indicated that radiation exposures at the monitoring locations 
did not significantly change, and no correlation appeared to exist 
between total annual reactor operations and annual exposures measured 
at the monitoring locations. Based on the NRC staff's review of the 
past 5 years of data, the NRC staff concludes that operation of the 
GSTR does not have any significant radiological impact on the 
surrounding environment. No changes in reactor operation that would 
affect radiation levels in the environment are expected as a result of 
the proposed action. Therefore, the NRC staff concludes that the 
proposed action would not have a significant radiological impact.
Environmental Effects of Accidents
    Accident scenarios are provided in the guidance in NUREG-1537, 
``Guidance for Preparing and Reviewing Applications for the Licensing 
of Non-Power Reactors,'' issued February 1996, and the results of the 
licensee's analysis was provided in Chapter 13 of the GSTR SAR. 
Typically, the most significant radiological fission product release 
accident considered at a research reactor is the maximum hypothetical 
accident (MHA) which for this reactor design is the rupture of one 
highly irradiated fuel element and the instantaneous release of the 
contained noble gases and halogen fission products into the air. The 
dose calculations conservatively assume no radioactive decay of the 
fission products prior to release. The licensee conservatively 
calculated doses to facility personnel and the maximum

[[Page 38742]]

potential doses to members of the public at various locations around 
the GSTR. The NRC staff performed independent calculations to verify 
that the licensee's calculated doses represented conservative estimates 
for the MHA. The details of these calculations are provided in the NRC 
staff's SE report that will be issued with the renewed license. The 
occupational radiation doses resulting from this postulated accident 
would be well below the 10 CFR 20.1201 limit of 5,000 mrem (50 mSv). 
The maximum calculated radiation doses for members of the public 
resulting from this postulated accident would be well below the 10 CFR 
20.1301 limit of 100 mrem (1 mSv).
    The licensee has not requested changes to the facility design or 
operating conditions as part of the license renewal. No changes are 
being made in the types or quantities of effluents that may be released 
offsite. The licensee has systems in place for controlling the release 
of radiological effluents and implements a radiation protection program 
to monitor personnel exposures and calculates releases of radioactive 
effluents. As discussed in the NRC staff's SE., 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. Accordingly, license renewal should not result in an 
increase in routine occupational or public radiation exposure. As 
discussed in detail in the NRC staff's SE., the proposed action will 
not significantly increase the probability or consequences of 
accidents. Therefore, license renewal would not change the 
environmental impact of facility operations. The NRC staff evaluated 
information contained in the licensee's application, as supplemented, 
and data reported to the NRC by the licensee for the last 5e 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 found that releases of radioactive material and personnel 
exposures were all well within applicable regulatory limits. Based on 
this evaluation, the NRC staff concluded that continued operation of 
the reactor for an additional 20 years should not have a significant 
environmental impact.
B. Non-Radiological Impacts
    The GSTR core is cooled by natural convection of demineralized 
light-water in the primary cooling system consisting of the reactor 
tank and heat removal system. Cooling of the reactor core occurs by 
natural convection of coolant through the core, with the heated coolant 
rising out of the core and into the bulk pool water. The heat removal 
system transfers heat to the secondary system by pumping primary 
coolant through the tube-side of a 1000 kilowatt rated shell and tube 
heat exchanger. The secondary system circulates water through the 
shell-side of the heat exchanger and a forced-air cooling tower. Forced 
air is directed perpendicular to the water flow in the cooling tower to 
cool the water. 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 in the unlikely event of a heat exchanger 
failure. Secondary coolant make-up water to the cooling tower is 
provided by city water and is automatically added as needed by a float-
type control valve. The addition of secondary coolant make-up water is 
based on the evaporative loss through the cooling tower, and, thus, is 
minimal with respect to the total capacity of city water. Release of 
thermal effluents from the GSTR cooling tower will not have a 
significant effect on the environment. No chemicals are used in the 
treatment of the primary or secondary coolant. No highly hazardous 
chemicals, toxins or reactives are present at the facility. No strong 
acids or bases are used or stored by the licensee. The facility does 
use small amounts (typically less than 50 milliliter) of chemicals for 
experiments, but these chemicals are of low toxicity, reactivity and 
corrosivity characteristics, and are transferred as licensed byproduct 
material as part of the experiment to the user. As such, the licensee 
generally maintains less than 1 gallon (3.8 liters) of any chemical at 
the facility.
    Given that the proposed action does not involve any changes in the 
design or operation of the reactor, and the heat load is dissipated to 
the environment by evaporative loss through a forced-air cooling tower, 
the NRC staff concludes that the proposed action will not have a 
significant impact on the local water supply.
National Environmental Policy Act Considerations
    The NRC has responsibilities that are derived from the National 
Environmental Policy Act 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.
1. Endangered Species Act
    The NRC staff conducted a search of Federally-listed species and 
critical habitats that have the potential to occur in the vicinity of 
the GSTR facility using the U.S. Fish and Wildlife Service (FWS) 
Environmental Conservation Online System Information for Planning and 
Conservation (IPaC) system. The IPaC system report identified 10 
Federally endangered or threatened species that may occur or could 
potentially be affected by the proposed action (ADAMS Accession No. 
ML16120A471). However, none of these species are likely to occur near 
the GSTR facility because the facility is located within the Denver 
Federal Center, a U.S. General Services Administration-operated 
property that houses office buildings, warehouses, laboratories, and 
special use space. The area was developed for Federal government 
operations in the 1940s and has remained in use since that time. 
Because the area enclosed by the Denver Federal Center was developed 
for government buildings, it does not provide suitable habitat for any 
Federally-listed species. Further, the IPaC report determined that no 
critical habitat is within the vicinity of the GSTR facility. 
Accordingly, the NRC concludes that the proposed license renewal of the 
GSTR facility would have no effect on Federally-listed species or 
critical habitats. Federal agencies are not required to consult with 
the FWS if they determine that an action will not have an effect on 
listed species or critical habitat (ADAMS Accession No. ML16120A505). 
Thus, the Endangered Species Act (ESA) does not require consultation 
for the proposed GSTR facility license renewal, and the NRC considers 
its obligations under ESA Section 7 to be fulfilled for the proposed 
action.
2. Coastal Zone Management Act
    The GSTR is not located within any managed coastal zones, nor would 
GSTR effluents and emissions impact any managed costal zones. 
Therefore, the NRC does not have obligations under CZMA for this 
proposed action.
3. National Historic Preservation Act
    The NHPA requires Federal agencies to consider the effects of their 
undertakings on historic properties. As stated in the Act, historic 
properties are any prehistoric or historic district, site, building, 
structure, or object included

[[Page 38743]]

in, or eligible for inclusion in the National Register of Historic 
Places (NRHP). The NRHP lists eleven historical sites in the Lakewood, 
Colorado area. None of the sites are closer than 0.5 miles (0.8 
kilometers) to the GSTR. Given the distance between the GSTR facility 
and these historical properties, continued operation of GSTR within the 
Nuclear Science Building would not impact any historical sites. The 
State Historic Preservation Office (SHPO) was contacted and the SHPO 
determined that license renewal would have no adverse effect on 
historic properties in the vicinity of the GSTR. Based on this 
information, the NRC finds that the potential impacts of license 
renewal would have no adverse effect on historic properties located in 
the vicinity of Building 15 of the Denver Federal Center and the GSTR.
4. Fish and Wildlife Coordination Act
    With regard to the GSTR, the licensee is not planning any water 
resource development projects, including any of the modifications 
relating to 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. Therefore, this action has no significant 
impact related to the FWCA.
5. 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 relicensing and the continued operation of the GSTR. Such effects 
may include human health, biological, cultural, economic, or social 
impacts.
    Minority Populations in the Vicinity of the GSTR--According to the 
2010 Census, about 34 percent of the total population (approximately 
930,000 individuals) residing within a 10-mile radius of the GSTR 
identified themselves as a minority. The largest minority population 
were people of Hispanic, Latino, or Spanish origin of any race 
(approximately 241,000 persons or 26 percent), followed by Black or 
African American (approximately 271,000 or 3 percent). According to the 
U.S. Census Bureau's 2010 census data, about 20 percent of the 
Jefferson County population identified themselves as minorities, with 
persons of Hispanic, Latino, or Spanish origin of any race comprising 
the largest minority (14.3 percent), followed by Asian (2.6 percent). 
According to the U.S. Census Bureau's 2014 American Community Survey 1-
Year Estimates, the minority population of Jefferson County, as a 
percent of the total population, had increased to about 21.3 percent.
    Low-income Populations in the Vicinity of the GSTR--According to 
the U.S. Census Bureau's 2009-2013 American Community Survey 5-Year 
Estimates, approximately 140,000 individuals (15.1 percent) residing 
within a 10-mile radius of the GSTR, were identified as living below 
the Federal poverty threshold. The 2013 Federal poverty threshold was 
$28,834 for a family of four.
    According to the U.S. Census Bureau's 2014 American Community 
Survey 1-Year Estimates, median household income for Colorado was 
$61,303, while 8.0 percent of families and 12.0 percent of the state 
population were found to be living below the Federal poverty threshold. 
Jefferson County had a higher median household income average ($70,714) 
and lower percentages of families (4.5 percent) and individuals (8.1 
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 this information and the analysis of human health and 
environmental impacts presented in this environmental assessment, the 
proposed relicensing would not have disproportionately high and adverse 
human health and environmental effects on minority and low-income 
populations residing in the vicinity of the GSTR.

Environmental Impacts of the Alternatives to the Proposed Action

    As an alternative to license renewal, the NRC considered denying 
the proposed action (i.e., the ``no-action'' alternative). If the NRC 
denied the request for license renewal, reactor operations would cease 
and decommissioning would be required. The NRC notes that, even with a 
renewed license, the GSTR will eventually be decommissioned, at which 
time the environmental effects of decommissioning would occur. 
Decommissioning would be conducted in accordance with an NRC-approved 
decommissioning plan which would require a separate environmental 
review under 10 CFR 51.21. Cessation of facility operations would 
reduce or eliminate radioactive effluents and emissions. However, as 
previously discussed in this environmental assessment, radioactive 
effluents and emissions from reactor operations constitute a small 
fraction of the applicable regulatory limits. Therefore, the 
environmental impacts of license renewal and the denial of the request 
for license renewal would be similar. In addition, denying the request 
for license renewal would eliminate the benefits of teaching, research, 
and services provided by the GSTR.

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 Amendment No. 10 to Facility 
Operating License No. R-113 for the GSTR, dated June 16, 2005, which 
extended the license expiration date from October 10, 2007, to February 
24, 2009, by removing the construction time, from the issuance date of 
Construction Permit No. CPRR-102 on October 10, 1967, to the issuance 
of Operating License No. R-113 on February 24, 1969.

Agencies and Persons Consulted

    In accordance with the agency's stated policy, on May 25, 2016, the 
staff consulted with the Colorado State Liaison Officer regarding the 
environmental impact of the proposed action. The consultation involved 
a telephone voice message with an explanation of the environmental 
review, and an electronic mail message with a copy of the details of 
this environmental assessment, and the NRC staff's findings. On May 27, 
2016, the State Liaison Officer responded, via electronic mail, that 
they understood the NRC staff review, and had no comments regarding the 
proposed action (ADAMS Accession No. ML16153A207).
    The NRC staff provided information about the proposed activity to 
the Colorado State Historic Preservation Officer for review in a letter 
dated January 26, 2011 (ADAMS Accession No. ML110310614). The staff 
requested a review concerning the historical assessment of the proposed 
action. On February 16, 2011, the Colorado Historic Preservation Office 
responded by letter (ADAMS Accession No. ML110600304) and concurred 
with the conclusions that no historical properties were affected by the 
proposed action.
    The NRC staff provided information about the proposed activity to 
the City of Lakewood, Department of Planning and Public Works for 
review in a letter dated September 9, 2011 (ADAMS

[[Page 38744]]

Accession No. ML112560231). The staff requested a review concerning the 
historical assessment of the proposed action. On November 16, 2011, the 
Manager, Planning Development Assistance responded by electronic mail 
(ADAMS Accession No. ML113210158) and concurred with the conclusions 
that no historical properties were affected by the proposed action.

III. Finding of No Significant Impact

    The NRC staff has prepared this EA as part of its review of the 
proposed action. On the basis of the EA included in Section II above 
and incorporated by reference in this finding, the NRC finds that there 
are no significant environmental impacts from the proposed action, and 
the proposed action will not have a significant effect on the quality 
of the human environment. The NRC staff has determined that a FONSI is 
appropriate, and decided not to prepare an environmental impact 
statement for the proposed action.

IV. Availability of Documents

    The following table identifies the environmental and other 
documents cited in this document and related to the NRC's FONSI. These 
documents are available for public inspection online through ADAMS at 
https://www.nrc.gov/reading-rm/adams.html or in person at the NRC's PDR 
as described previously.

------------------------------------------------------------------------
                 Document                       ADAMS Accession No.
------------------------------------------------------------------------
United States Geological Survey--Safety    ML092120136
 Analysis Report, Technical
 Specifications, and Environmental Report
 to Support License Renewal (redacted
 version), January 5, 2009.
U.S. Geological Survey TRIGA Reactor       ML103340090
 Response to the RAI Concerning R 113
 License Renewal, November 24, 2010.
Letter dated 01/26/11; Subject: Request    ML110310614
 for a Section 106 Review Under the
 National Historic Preservation Act for
 the U.S. Geological Survey TRIGA Reactor
 in Lakewood, Colorado, January 26, 2011.
Colorado Historical Society, Letter dated  ML110600304
 2/16/11, RE: Request for a Section 106
 Review under NHPA for USGS TRIGA
 Reactor, Lakewood, CO, February 16, 2011.
Letter dated 09/09/11; Subject: Request    ML112560231
 for a Section 106 Review Under the
 National Historic Preservation Act for
 the U.S. Geological Survey TRIGA Reactor
 in Lakewood, Colorado; from T. Jackson,
 NRC, to W. Clayton, City of Lakewood,
 CO, September 9, 2011.
City of Lakewood E-mail dated 11/16/11,    ML113210158
 Subject: Section 106 Review of USGS
 TRIGA Reactor in Lakewood, November 16,
 2011.
Response to Letter of February 1, 2011     ML110480046
 Concerning R-113 License Renewal,
 February 11, 2011.
Response to Questions 23.1, 23.2, and      ML110950059
 23.3 of the Referenced RAI, March 28,
 2011.
U.S. Geological Survey--Response to        ML11138A027
 Questions 22.1, 22,2, 25.1, 25.2, 25.3,
 25.4, and 25.6 of the Referenced RAI,
 May 12, 2011.
U.S. Geological Survey, Response to        ML11181A305
 Request for Additional Information for
 Questions 17.1 and 17.2, June 29, 2011.
Response to Question 2 of the Referenced   ML11214A091
 RAI, July 27, 2011.
Response to Question 1 of the Referenced   ML112500522
 RAI, August 30, 2011.
Response to Request for Additional         ML11277A013
 Information to Question 20, September
 26, 2011.
U.S. Geological Survey TRIGA Reactor       ML11314A106
 (GSTR) Response to Question 6 of the
 Referenced RAI, October 31, 2011.
U.S. Geological Survey--Redacted--         ML113460014
 Licensee Response to NRC Request for
 Additional Information Questions 7 and
 8, License Renewal, November 30, 2011.
U.S. Geological Survey--Redacted--         ML120240003
 Licensee Response to NRC Request for
 Additional Information Question 15.3,
 January 3, 2012.
U.S. Geological Survey TRIGA Reactor--     ML12068A138
 Response to Question 15.2 of the Request
 for Additional Information dated
 September 29, 1010, January 27, 2012.
U.S. Geological Survey TRIGA Reactor       ML12039A173
 (GSTR)--Response to Question 18 of a
 Request for Additional Information dated
 September 29, 2010, January 27, 2012.
U.S. Geological Survey TRIGA Reactor,      ML12100A097
 Response to Request for Additional
 Information to Question 14, March 28,
 2012.
U.S. Geological Survey TRIGA Reactor       ML12128A429
 (GSTR)--Response to Question 16 of the
 Referenced RAI, April 27, 2012.
U.S. Geological Survey, Responses to       ML12151A407
 Questions 26 and 27 of the Referenced
 RAI, May 18, 2012.
U.S. Geological Survey--Response to        ML12160A064
 Request for Additional Information (RAI)
 Question 14, May 31, 2012.
U.S. Geological Survey TRIGA Reactor       ML12200A055
 (GSTR)--Response to Question 3 of the
 Referenced RAI, June 29, 2012.
U.S. Geological Survey TRIGA Reactor       ML12220A525
 Response to Question 21 of the
 Referenced RAI dated September 29, 2010,
 July 31, 2012.
Responses to Questions 9, 10, 11, 12,      ML12251A231
 15.1, 23.4, 24, and 25.5; Along with a
 Corrected Copy of the Proposed Technical
 Specifications (Chapter 14) of the SAR,
 August 30, 2012.
U.S. Geological Survey--Redacted--         ML12334A001
 Response to NRC Request for Additional
 Information dated October 2, 2012,
 November 16, 2012.
U.S. Geological Survey--Redacted--         ML13052A179
 Responses to NRC Request for Additional
 Information dated October 2, 2012 and
 Telephone Conference dated December 20,
 2012, February 8, 2013.
Redacted USGS RAI Clarification            ML13162A662
 Information Needed to Support the USGS
 License Renewal SAR (ME1593), May 17,
 2013.
Follow-up Safety Analysis Responses from   ML13311A047
 letter dated July 15, 2013, October 31,
 2013.
Submission of Revised Technical            ML14325A646
 Specifications, Chapter 14, November 3,
 2014.
Redacted Version--U.S. Geological Survey   ML14338A196
 TRIGA Reactor Request for Additional
 Information Responses to RAI Questions
 15.3 and 28, November 24, 2014.
Revision of Proposed Technical             ML15261A042
 Specifications, September 8, 2015.
U.S. Geological Survey, Responses to RAI   ML16042A575
 Questions 1a, 1b, and 1c, January 22,
 2016.
U.S. Geological Survey RAI letter          ML16110A008
 Redacted, April 1, 2016.
U.S. Fish and Wildlife Service, UGSG       ML16120A471
 Training, Research, Isotope Production,
 General Atomics Research Reactor License
 Renewal, IPaC Trust Resources Report,
 April 29, 2016.
U.S. Fish and Wildlife Service,            ML16120A505
 Endangered Species Consultations
 Frequently Asked Questions, July 15,
 2013.
Colorado State Liaison Officer E-mail,     ML16153A207
 RE: Review of the draft Environmental
 Assessment Supporting License Renewal of
 the USGS Research Reactor, May 27, 2016.
------------------------------------------------------------------------



[[Page 38745]]

    Dated at Rockville, Maryland, this 6th day of June 2016.

    For the Nuclear Regulatory Commission.
Alexander Adams, Jr.,
Chief, Research and Test Reactors Licensing Branch, Division of Policy 
and Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. 2016-14078 Filed 6-13-16; 8:45 am]
 BILLING CODE 7590-01-P