82 FR 1364 - Rhode Island Atomic Energy Commission

NUCLEAR REGULATORY COMMISSION

Federal Register Volume 82, Issue 3 (January 5, 2017)

Page Range		1364-1370
FR Document		2016-31980
The U.S. Nuclear Regulatory Commission (NRC) is considering renewal of Facility License No. R-95, held by the Rhode Island Atomic Energy Commission (RIAEC or the licensee), for the continued operation of the Rhode Island Nuclear Science Center Reactor (RINSC reactor or the facility), located in the Narragansett, Washington County, Rhode Island. The NRC is issuing an environmental assessment (EA) and finding of no significant impact (FONSI) associated with the renewal of the license.
Federal Register, Volume 82 Issue 3 (Thursday, January 5, 2017)
[Federal Register Volume 82, Number 3 (Thursday, January 5, 2017)]
[Notices]
[Pages 1364-1370]
From the Federal Register Online  [www.thefederalregister.org]
[FR Doc No: 2016-31980]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-193; NRC-2016-0213]


Rhode Island Atomic Energy Commission

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 License No. R-95, held by the Rhode Island Atomic 
Energy Commission (RIAEC or the licensee), for the continued operation 
of the Rhode Island Nuclear Science Center Reactor (RINSC reactor or 
the facility), located in the Narragansett, Washington County, Rhode 
Island. 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 on January 5, 2017.

ADDRESSES: Please refer to Docket ID NRC-2016-0213 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 http://www.regulations.gov and search for Docket ID NRC-2016-0213. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-415-
3463; email: [email protected]. 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 http://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 [email protected]. 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 OWFN-01F21, One White Flint North, 
11555 Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Patrick G. Boyle, Office of Nuclear 
Reactor Regulation, U.S. Nuclear Regulatory Commission, Rockville, MD 
20852. Telephone: 301-415-3936; email: [email protected].

SUPPLEMENTARY INFORMATION: 

I. Introduction

    The NRC is considering issuance of a renewed Facility Operating 
License No. R-95, held by RIAEC, which would authorize continued 
operation of the RINSC reactor, located in Narragansett, Washington 
County, Rhode Island. 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 staff prepared an EA documenting its 
environmental review. Based on the results of the EA that follows, the 
NRC has determined not to prepare an environmental impact statement for 
the proposed renewed license and is issuing a FONSI in accordance with 
10 CFR 51.32, ``Finding of no significant impact.''

II. Environmental Assessment

Facility Site and Environs

    The RINSC reactor is located on the University of Rhode Island 
Narragansett Bay Campus. The RINSC facility consists of one building 
that houses the reactor and support areas. The confinement section of 
the reactor building is constructed primarily of concrete, brick, 
steel, and aluminum. The RINSC site comprises the reactor building and 
a small area immediately surrounding it, partially bounded by a chain-
link fence. Adjacent to the reactor site are athletic facilities to the 
north and west, fields and parking lots to the east, and academic and 
research buildings to the south. Surrounding areas are well developed 
with offsite land use mostly residential in nature. The nearest 
residences are located approximately 500 meters (1,640 feet) west-
northwest and south of the facility.
    The RINSC reactor is a pool-type, water moderated and cooled 
research reactor licensed to operate at a thermal steady-state power 
level of 2 megawatts (MWt). The reactor was designed to permit later 
conversion to a steady-state power level of 5 MWt. The fuel is located 
at the bottom of an aluminum-lined concrete pool with a volume of 
approximately 40,000 gallons (151,000 liters) and a depth of 32 feet 
(9.7 m). The reactor is fueled with standard plate-type low-enriched 
uranium fuel provided by the Department of Energy.
    The RINSC reactor uses demineralized water for primary coolant, 
shielding, and as a reactor moderator and city water for secondary 
coolant. At power levels below 0.1 MWt, the core can be cooled by 
natural convection of water through the reactor core and at power 
levels above 0.1 MWt the core is cooled by forced convection of water 
through the reactor core. In natural convection mode cooling, heat from 
the core is transferred to the primary cooling water in the pool where 
it is dissipated to the surrounding environment. In forced convection 
mode cooling, heat is transferred from the primary cooling water to two 
heat exchangers, which pass the heat to the secondary cooling loops, 
which in turn dissipate the heat to the surrounding environment via two 
cooling towers. Operation of the primary and secondary cooling systems 
are checked on a daily basis prior to forced convection reactor 
operation. During this checkout, the performance of each system is 
monitored with emphasis on pump

[[Page 1365]]

outlet pressures, pressure differentials and system flow rates. The 
licensee conducts periodic tests of the secondary water for sodium-24 
which would indicate a leak from the primary water into the secondary 
water.
    During normal operation of the RINSC reactor, the only significant 
airborne radioactive effluent is Argon-41 (Ar-41). The primary liquid 
radioactive effluents produced during normal operation include 
miscellaneous neutron activation products in the primary coolant, many 
of which are deposited in the mechanical filter and demineralizer 
resins and, therefore, disposed of as solid radioactive waste. Non-
routine liquid radioactive wastes can result from decontamination or 
maintenance activities, such as filter or resin replacements. Solid 
radioactive wastes include waste generated from reactor maintenance 
operations and laboratory wastes from experiments. Much of the solid 
radioactive waste generated at the RINSC facility is held in a 
restricted area and allowed to decay to background levels and then 
disposed of as non-radioactive waste. Solid radioactive waste that is 
not decayed in storage is transferred to a low-level waste broker for 
appropriate disposal.
    The RIAEC maintains a Radiation Protection Program, which involves 
regular monitoring of airborne, liquid, and solid gamma and beta 
radiation to ensure that any effluent releases are within the limits of 
10 CFR part 20, ``Standards For Protection Against Radiation.'' The 
current environmental program consists of radiation area monitors 
(RAMs), continuous air monitors (CAMs), portable radiation survey 
instruments, personnel monitors, and stack gas and particulate 
monitors. Perimeter monitoring at the RINSC facility consists of 
Optically-Stimulated Luminescent Dosimeters (OLDs) which detect X-ray 
and gamma radiation.
    A detailed description of the reactor and its operations can be 
found in the Safety Analysis Report (SAR) for the RINSC reactor 
submitted by RIAEC with its renewal application.

Description of the Proposed Action

    The proposed action would renew Facility Operating License No. R-95 
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 May 3, 2004, as supplemented on January 19, February 
4, August 6, August 18, September 3, September 8, November 26, December 
7, and December 14, 2010; January 24, February 24, and July 15, 2011; 
March 15, September 16, and December 19, 2013; February 24, April 28, 
and June 30, 2014; August 7 and August 11, 2015; and January 20, 
February 26, March 1, April 21, July 20, October 6, November 1, 
November 14, December 1, December 8, December 13, and December 15, 2016 
(collectively referred to as ``the renewal application''). Initially, 
the operating license was to expire at midnight on August 27, 2002, but 
a construction time recapture license amendment issued on July 28, 2000 
extended the license expiration date to July 21, 2004. Because of the 
timely renewal provision contained in 10 CFR 2.109(a), the licensee is 
permitted to continue operation of the reactor under the terms and 
conditions of its operating license until the license renewal 
application before the NRC has been finally determined. The proposed 
renewal would authorize continued operation of the reactor for an 
additional 20 years from the date of issuance of the renewed license.

Need for the Proposed Action

    The proposed action is needed to allow the continued operation of 
the RINSC reactor to routinely provide teaching, research, and services 
to numerous institutions for a period of 20 years from the date of 
issuance of the renewed license.

Environmental Impacts of the Proposed Action

    The environmental impacts of the proposed action are discussed 
below. As discussed below, the proposed action will not have a 
significant environmental impact. In addition, the proposed action will 
not require any physical changes to the facility and the impacts are 
similar to those occurring during past operations.

A. Radiological Impacts

Environmental Effects of Reactor Operations
    The only significant gaseous radioactive effluent resulting from 
the operation of the RINSC reactor is Ar-41. This nuclide is released 
to the environment from the reactor building from an exhaust stack on 
the roof that combines the ventilation exhausts from both the main and 
the purge systems. The stack discharge length is 115 feet (35 meters). 
Nitrogen-16 (N-16) is also produced during reactor operation, but its 
release from the reactor stack is insignificant because the half-life 
of N-16 is approximately 7 seconds and most of the N-16 produced in the 
reactor coolant would decay before reaching the stack. Therefore Ar-41 
is the most significant radionuclide released as a gaseous effluent 
during normal reactor operations.
    The licensee's Technical Specifications require that public doses 
from Ar-41 not exceed the 100 millirem (mrem) annual public dose limit 
in 10 CFR 20.1301, ``Dose limits for individual members of the 
public.'' The Ar-41 release rate would reach a maximum during 
continuous operation at full power. Historical data shows that the 
reactor generates approximately 0.14  0.03 Curie (Ci) of 
Ar-41 per MW hour of operation. Using the Environmental Protection 
Agency COMPLY computer code, the licensee calculated the dose to the 
maximally-exposed member of the public located 100 meters (328 feet) 
from the stack to be 0.021 mrem (0.00021 millisieverts (mSv)) per Ci of 
Ar-41 released. Using this result, the licensee also calculated that an 
annual release of 476 Ci of Ar-41 (corresponding to approximately 3,400 
MW-hours, or 1,700 hours of operation at full licensed power) from the 
RINSC reactor would correspond to a maximum public dose of 10 mrem 
(0.10 mSv) per year. The NRC staff finds the licensee's calculations to 
be reasonable and conservative. Seven annual operational reports 
covering the period July 2009 through June 2016 (each annual report 
covers a July through June reporting period) show that the maximum 
recorded release of Ar-41 in 1 year was 129.4 Ci, which would result in 
a dose of 2.7 mrem (0.027 mSv) in 1 year to a member of the public. 
This is less than 3 percent of the 100 mrem (1 mSv) per year limit 
specified in 10 CFR 20.1301. The maximum radiation dose of 2.7 mrem 
(0.027 mSv) in 1 year also demonstrates compliance with the as low as 
is reasonably achievable (ALARA) air emissions dose constraint of 10 
mrem (0.10 mSv) specified in 10 CFR 20.1101, ``Radiation protection 
programs,'' paragraph(d).
    Liquid radioactive wastes are produced as a result of normal 
operation of the RINSC reactor, and typically consist of miscellaneous 
neutron activation product impurities in the reactor coolant. Since 
most of these activation products can be removed from the reactor 
coolant by collection on the mechanical filters and the demineralizer 
resins, most of these radioactive materials are typically disposed as 
solid radioactive sources. While some non-routine liquid radioactive 
waste could be generated due to decontamination or maintenance 
activities, the amounts, based on a review of the licensee's past 
operating experience, as reported in their annual reports, have been 
and are expected to remain a small volume. Liquid

[[Page 1366]]

radioactive wastes at the RINSC facility are allowed to decay in 
storage, are disposed of into the sanitary sewer in accordance with 10 
CFR 20.2003, ``Disposal by release into sanitary sewerage,'' or, when 
necessary, are packaged and transported offsite for disposal. Annual 
operational reports covering the period July 2009 through June 2016 
show that the licensee complied with the limits on discharges to the 
sanitary sewer in 10 CFR part 20, Appendix B.
    Low-level solid radioactive waste generated from reactor operations 
typically includes laboratory wastes such as irradiated plastics, 
contaminated tools, towels, as well as reactor demineralizer resins and 
particulate filters. Any radioactive waste that contains radionuclides 
with half-lives of less than 90 days is allowed to decay in storage and 
is then disposed of as normal solid waste. Historically, one or two 55-
gallon drums of solid waste are generated each year, with the activity 
being in the microcurie range. This waste is disposed of by 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 licensee has entered into a contract with 
the U.S. Department of Energy (DOE) that provides that DOE retains 
title to the fuel utilized at RINSC reactor and that DOE is obligated 
to take the fuel from the site for final disposition.
    As described in Chapter 11 of the RINSC reactor SAR, personnel 
exposures are well within the limits set by 10 CFR 20.1201, 
``Occupational dose limits for adults,'' and are ALARA. The licensee 
tracks exposures of personnel monitored with dosimeters, and exposures 
are usually less than 10 percent of the occupational limit of 5,000 
mrem (50 mSv) per year. Area thermo-luminescent dosimeter monitors 
mounted in the control room and the reactor bay provide an additional 
monthly measurement of total radiation exposures at those locations. 
Annual operational reports covering the period July 2009 through June 
2016 show that the personnel doses were well within the 10 CFR 20.1201 
limits. No changes in reactor operation that would lead to an increase 
in occupational dose are expected or proposed as a result of the 
proposed action.
    The radiation monitoring systems associated with reactor operations 
at the RINSC facility are provided and maintained as a means of 
ensuring compliance with radiation limits established under 10 CFR part 
20, ``Standards for Protection against Radiation.'' The RINSC facility 
monitoring systems consist of RAMs, CAMs, portable radiation survey 
instruments, perimeter monitors, and stack gas and particulate 
monitors. The stack particulate and gas monitoring systems measure the 
beta-gamma activity emitted by radioactive particulates and the 
activity of gaseous radioactive nuclides, respectively, that are 
exhausted through the RINSC facility stack. Perimeter monitoring at 
RINSC facility consists of OLDs which detect X-ray and gamma radiation.
    The licensee conducts a monitoring program to record and track the 
radiological impact of reactor operation on the surrounding 
unrestricted area. The program consists of quarterly exposure 
measurements at three locations outside the reactor building using 
OLDs. The licensee then applies an occupancy factor to determine the 
final exposure measurement. The licensee's radiation safety officer 
administers the program and maintains the appropriate records. Annual 
operational reports covering the period July 2009 through June 2016 
show that radiation exposures at the monitoring locations were below 
the limits to the public as required by 10 CFR part 20. Year-to-year 
trends in exposures are consistent between monitoring locations. Also, 
no correlation exists between total annual reactor operation and annual 
exposures measured at the monitoring locations. Based on review of data 
for the years 2009 through 2016, the NRC staff finds that operation of 
the RINSC 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 or proposed as a result 
of the proposed action.
    Because occupational and public exposures are below regulatory 
limits, the NRC staff concludes that the proposed action would not have 
a significant radiological impact.
Environmental Effects of Accidents
    Accident scenarios are discussed in Chapter 13 of the RINSC SAR. 
The accidents analyzed in Chapter 13 cover a range of anticipated 
events, including a postulated accident involving a fission product 
release with radiological consequences that exceed those of any 
accident considered to be credible. This limiting accident is referred 
to as the maximum hypothetical accident (MHA). The licensee considers 
the uncontrolled release of the gaseous fission products from a 
fissionable experiment to be the MHA. In the scenario used by the 
licensee, an experiment containing fissionable material fails, and the 
gaseous fission products in the experiment are released into the air of 
the reactor building. From the reactor building, the release would 
continue to the environment. The licensee calculated doses to facility 
personnel during a five minute evacuation duration, and also calculated 
the dose to a member of the public outside the facility during the two 
hours it would take the entire plume of released radioactive material 
to pass. The licensee estimated an occupational dose of 1,570 mrem 
(15.7 mSv), and a dose of 100 mrem (1 mSv) to the maximally-exposed 
member of the public. The NRC staff reviewed the licensee's 
calculations, and found them to be generally reasonable and acceptable. 
The NRC staff also performed independent calculations to verify that 
the licensee's calculated doses represented conservative estimates for 
the MHA. The NRC staff estimated an occupational dose of 4,100 mrem 
(41.0 mSv), and a dose of 88 mrem (0.88 mSv) to the maximally-exposed 
member of the public. The details of these calculations are provided in 
the safety evaluation report that the NRC staff is preparing to 
document the safety review of the application for a renewed license. 
The NRC staff estimates that the occupational radiation doses resulting 
from the postulated MHA would be below the 10 CFR 20.1201 limit of 
5,000 mrem (50 mSv). The NRC staff also estimates that the maximum 
radiation doses for members of the public resulting from the postulated 
MHA would be at or below the 10 CFR 20.1301 limit of 100 mrem (1 mSv).
    The licensee has systems in place for controlling the release of 
radiological effluents, and implements a radiation protection program 
to monitor personnel exposures and releases of radioactive effluents. 
The licensee's systems and radiation protection program are appropriate 
for the types and quantities of effluents expected to be generated by 
continued operation of the reactor. The NRC also staff evaluated 
information contained in the licensee's renewal application and data 
the licensee reported to the NRC for the last 7 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. Because the licensee 
has not requested any changes to the facility design or operating 
conditions as part of the application for license renewal, the proposed 
action would not significantly

[[Page 1367]]

increase the probability or consequences of accidents, would not 
significantly change the types or quantities of effluents that may be 
released off-site, and would not significantly increase individual or 
cumulative occupational or public radiation exposure. Based on its 
evaluation, the NRC staff concludes that continued operation of the 
reactor would not have a significant environmental impact.

B. Non-Radiological Impacts

    The proposed action does not involve any change in the operation of 
the reactor, change in the emissions or heat load dissipated to the 
environment, or construction or other land disturbance activities. The 
proposed action would not result in any land use changes or increase in 
noise or air emissions, and would not have a significant impact on air 
quality, noise or visual, terrestrial or aquatic resources. The 
proposed license renewal would not affect surface water or groundwater 
resources, because water is supplied through the city and no changes in 
facility operations are proposed. Heat produced cooling the reactor is 
ultimately disposed to the environment through the secondary cooling 
system and cooling tower. There are no increased thermal effects on the 
environment in the proposed action. The licensee uses no chemical 
treatments in the secondary cooling system. Hazardous chemicals may be 
used in experiments at the RINSC facility, but no releases of 
potentially hazardous chemicals to the environment occur during normal 
facility operation. Disposal of non-radioactive waste, including 
hazardous chemicals, generated by individuals associated with the 
University of Rhode Island, is conducted by the campus Department of 
Safety and Risk Management in accordance with EPA regulations. The 
Safety and Risk Management organization provides training for users, 
performs inspections, and complies with OSHA and EPA regulations. 
Therefore, the NRC staff concludes that the proposed action would have 
no significant non-radiological impacts.

Other Applicable Environmental Laws

    In addition to the National Environmental Policy Act, which 
requires Federal agencies to consider the environmental impacts of 
proposed actions, the NRC has responsibilities that are derived from 
other environmental laws, which include the Endangered Species Act, 
Coastal Zone Management Act, Fish and Wildlife Coordination Act, 
National Historic Preservation Act, and Executive Order 12898, 
``Federal Actions to Address Environmental Justice in Minority 
Populations and Low-Income Populations.'' The following presents a 
brief discussion of impacts associated with resources protected by 
these laws and related requirements.
1. Endangered Species Act (ESA)
    The ESA was enacted to prevent further decline of endangered and 
threatened species and restore those species and their critical 
habitat. Section 7 of the ESA requires Federal agencies to consult with 
the U.S. Fish and Wildlife Service (FWS) or National Marine Fisheries 
Service (NMFS) regarding actions that may affect listed species or 
designated critical habitats. The NRC staff conducted a search of 
federally listed species and critical habitats that have the potential 
to occur in the vicinity of the RINSC facility using the FWS's 
Environmental Conservation Online System Information for Planning and 
Conservation system. Eight Federally-listed species occur in Washington 
County: The American burying beetle (Nicrophorus americanus), hawksbill 
sea turtle (Eretmochelys imbricata), leatherback sea turtle 
(Dermochelys coriacea), northern long-eared bat (Myotis 
septentrionalis), piping plover (Charadrius melodus), red knot 
(Calidris canutus rufa), roseate tern (Sterna dougallii dougallii), and 
sandplain gerardia (Agalinis acuta). However, none of these species are 
likely to occur near the RINSC reactor because the facility is located 
on the University of Rhode Island Narragansett Bay Campus, which does 
not provide suitable habitat for Federally listed species because it 
has been developed, and in use, for research and educational purposes 
for many decades. Additionally, operation of the RINSC reactor has no 
direct nexus to the natural environment that could otherwise affect 
federally listed species. Accordingly, the NRC staff concludes that the 
proposed license renewal of the RINSC reactor 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 affect listed species or critical habitats (ADAMS Accession No. 
ML16120A505). Thus, the ESA does not require consultation for the 
proposed RINSC reactor license renewal, and the NRC staff considers its 
obligations under ESA Section 7 to be fulfilled for the proposed 
action.
2. Coastal Zone Management Act (CZMA)
    The CZMA, in part, encourages States to preserve, protect, develop, 
and restore coastal resources. Applicants for Federal licenses to 
conduct an activity that affects any land or water use or natural 
resource of the coastal zone of a state must provide a certification in 
that the proposed activities complies with the State's approved coastal 
zone management program and will conduct activities consistent with 
that program.
    Rhode Island's approved coastal zone includes the area encompassed 
within the State's seaward boundary (3 miles (4.8 kilometers)) to the 
inland boundaries of the State's 21 coastal municipalities, of which 
Narragansett is one. Although the RINSC reactor is located within the 
State's coastal zone, the proposed license renewal is not reasonably 
likely to affect any land or water use or natural resource of the 
coastal zone, and thus, the CZMA consistency certification process does 
not apply. Therefore, the NRC staff finds that the licensee does not 
need to provide a certification under the CZMA.
3. Fish and Wildlife Coordination Act (FWCA)
    The FWCA requires Federal agencies that license water resource 
development projects to consult with the FWS (or NMFS, when applicable) 
and the State wildlife resource agencies regarding the potential 
impacts of the project on fish and wildlife resources.
    The proposed license renewal does not involve 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, no coordination with other agencies 
pursuant to the FWCA is required for the proposed action.
4. National Historic Preservation Act (NHPA)
    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 in, or eligible for inclusion in the 
National Register of Historic Places (NRHP).
    The NRHP lists one historic property on the University of Rhode 
Island Narragansett Bay Campus, the Narragansett Baptist Church. The 
location of the Narragansett Baptist Church is approximately 1,000 feet 
(304.8 meters) northwest of the RINSC facility. Operation of the RINSC 
reactor has not likely had any impact on this property. A request for a 
Section 106 project review was submitted to the

[[Page 1368]]

State Historic Preservation Officer (SHPO) regarding this undertaking 
and determination. By letter dated December 19, 2013, the Rhode Island 
SHPO concurred that this action would not affect any historic 
properties (ADAMS Accession No. ML14006A420). Based on this 
information, the NRC staff finds that the proposed license renewal and 
the continued operation of the RINSC reactor would have no adverse 
effect on historic properties located near the RINSC reactor.
5. Executive Order 12898--Environmental Justice
    Executive Order 12898, ``Federal Actions to Address Environmental 
Justice in Minority Populations and Low-Income Populations,'' 59 FR 
7629 (February 16, 1994), directs agencies to identify and address the 
disproportionately high and adverse human health or environmental 
effects of their actions on minority and low-income populations, to the 
greatest extent practicable and permitted by law.
    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 RINSC 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 RINSC reactor, and all are exposed 
to the same health and environmental effects generated from activities 
at the RINSC reactor.
    Minority Populations in the Vicinity of the RINSC Reactor--
According to the U.S. Census Bureau's 2010 Census, approximately 12 
percent of the total population (approximately 125,000 individuals) 
residing within a 10-mile radius of the RINSC reactor identified 
themselves as minorities. The largest minority populations were 
Hispanic, Latino, or Spanish origin of any race (approximately 4,900 or 
4 percent) followed by Black or African American (approximately 3,700 
or 3 percent). According to the 2010 Census, 7.6 percent of the 
Washington County population identified themselves as minorities, with 
persons of Hispanic, Latino, or Spanish origin of any race, Asians, and 
Black or African Americans comprising the largest minority populations 
(2.4 percent, 2.1 percent, and 2.0 percent, respectively). According to 
the U.S. Census Bureau's 2015 American Community Survey 1-year 
Estimates, the minority population of Washington County, as a percent 
of the total population, had increased to about 9 percent.
    Low-income Populations in the Vicinity of the RINSC Reactor--
According to U.S. Census Bureau's 2010-2014 American Community Survey 
5-Year Estimates, approximately 11,000 persons and 1,500 families 
(approximately 10 and 5 percent, respectively) residing within a 10-
mile radius of the RINSC reactor were identified as living below the 
Federal poverty threshold. The 2014 Federal poverty threshold was 
$24,230 for a family of four. According to the U.S. Census Bureau's 
2015 American Community Survey Census 1-Year Estimates, the median 
household income for the State of Rhode Island was $58,073 while 
approximately 10 percent of families and 14 percent of the state 
population were found to be living below the Federal poverty threshold. 
Washington County had a higher median household income average 
($72,453) and a lower percent of families (8 percent) and persons (10 
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 proposed 
license renewal are expected to continue at current levels, and would 
be below regulatory limits. No significant visual or noise impacts are 
expected to result from the proposed action. Based on this information 
and the analysis of human health and environmental impacts presented in 
this EA, 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 RINSC reactor.

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 (sooner than if a renewed license 
were issued) and the environmental effects of decommission would occur. 
Decommissioning would be conducted in accordance with an NRC-approved 
decommissioning plan, which would require a separate environmental 
review under 10 CFR part 51.21. Cessation of reactor operations would 
reduce or eliminate radioactive effluents. However, as previously 
discussed in this EA, radioactive effluents 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 RINSC reactor.

Alternative Use of Resources

    The proposed license renewal does not involve the use of any 
different resources or significant quantities of resources beyond those 
previously considered in the issuance of Facility License No. R-95 on 
July 21, 1964, which authorized RIAEC to operate the RINSC reactor, the 
license amendment issued on September 10, 1968, which authorized 
operation up to a maximum of 2 MWt, and the license amendment issued on 
March 17, 1993, which authorized the conversion from highly-enriched 
uranium fuel to low-enriched uranium fuel in the RINSC reactor.

Agencies and Persons Consulted

    With the exception of the Rhode Island SHPO as previously described 
in this EA, the NRC staff did not enter into consultation with any 
other Federal agencies or with the State of Rhode Island regarding the 
environmental impact of the proposed action. However, on December 20, 
2016, the NRC notified the Rhode Island State official, Mr. Paul 
D'Abbraccio, Radiological Emergency Preparedness Program Manager, of 
the Rhode Island Emergency Management Agency of the proposed action. 
Mr. Paul D'Abbraccio responded by email on December 22, 2016 and had no 
comments.

III. Finding of No Significant Impact

    The NRC is considering issuance of a renewed Facility License No. 
R-95, held by the RIAEC, which would authorize the continued operation 
of the RINSC reactor for an additional 20 years from the date of 
issuance of the renewed license.
    On the basis of the EA included in Section II of this notice and 
incorporated by reference in this finding, the NRC staff finds that the 
proposed action will not have a significant impact on the quality of 
the human environment. The proposed action would result in no 
significant impacts on terrestrial, surface or groundwater resources, 
or the radiological environment. In addition, the proposed action will 
not affect Federally-protected species or affect any designated 
habitat. The NRC staff's

[[Page 1369]]

evaluation considered information provided in the licensee's 
application, as supplemented, and the NRC staff's review of related 
environmental documents. Section IV below lists the environmental 
documents related to the proposed action and includes information on 
the availability of these documents. Accordingly, the NRC has 
determined not to prepare an environmental impact statement for the 
proposed action.

IV. Availability of Documents

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

------------------------------------------------------------------------
                Document                       ADAMS  accession No.
------------------------------------------------------------------------
``Rhode Island Atomic Energy Commission-- ML14038A386
 `Requesting Renewal of Operating
 License R-095 (Enclosure 2)' [REDACTED
 Safety Analysis Report],'' May 3, 2004.
``Rhode Island Atomic Energy Commission,  ML041270519
 Requesting Renewal of Operating License
 R-095,'' May 3, 2004.
``Response to Request for Additional      ML100270176
 Information Concerning Plans for
 Decommissioning Facility at the End of
 Useful Life Ref Item 3 Parts a, b, and
 c,'' January 19, 2010.
``Rhode Island Nuclear Science Center,    ML16340A068
 Appendix A to Safety Analysis Report,
 Information on Ar-41 and N-16,''
 (received December 5, 2016), February
 4, 2010.
``Rhode Island Nuclear Science Center     ML102240257
 Reactor Submittal of Response to
 Request for Additional Information Re
 License Renewal,'' August 6, 2010.
``Responding to Requests for Additional   ML102360440
 Information (RAI) regarding our
 Analysis of the Maximum Hypothetical
 Accident (MHA) for Renewal of License R-
 95,'' August 18, 2010.
``Memorandum Steady-State Thermal-        ML16062A376
 Hydraulic Analysis for
 Forced[dash]Convective Flow in the
 Rhode Island Nuclear Science (RINSC)
 Reactor,'' September 3, 2010.
``Rhode Island Atomic Energy Commission,  ML16279A516
 Fourth Response to Request for
 Additional Information dated April 23,
 2010 (Redacted),'' September 8, 2010.
``Rhode Island Atomic Energy Commission   ML16279A518
 Fifth Response to April 13, 2010
 Request for Additional Information
 (Regarding License Renewal redacted),''
 November 26, 2010.
``Rhode Island Atomic Energy Commission-- ML103490242
 Response to Requests for Additional
 Information Regarding Aging Issues
 Raised in RAIs,'' December 7, 2010.
``Rhode Island Atomic Energy Commission   ML16279A519
 Response to April 13, 2010, Request for
 Additional Information Regarding
 License Renewal Technical
 Specifications (Redacted),'' December
 14, 2010.
``Reply to your Request for Additional    ML110320416
 Information (RAI) dated April 13, 2010,
 regarding License Renewal for the Rhode
 Island Nuclear Science Center Reactor
 (RINSC),'' January 24, 2011.
``Letter re: Request for Additional       ML110600699
 Information dated April 13, 2010
 Regarding License Renewal for the Rhode
 Island Nuclear Science Center Reactor
 (RINSC),'' February 24, 2011.
``Rhode Island Atomic Energy Commission   ML11202A287
 Response to Request for Additional
 Information Regarding License
 Renewal,'' July 15, 2011.
``Rhode Island Atomic Energy Commission   ML16279A520
 Tenth Response to the April 13, 2010,
 Request for Additional Information
 Regarding License Renewal (Redacted),''
 July 15, 2011.
``Rhode Island Atomic Energy Commission   ML16279A521
 Responses to Request for Additional
 Information Regarding License Renewal
 (Redacted),'' July 15, 2011.
``Rhode Island Nuclear Science Center     ML11202A290
 Tenth Response to NRC Request for
 Additional Information dated April 13,
 2010, Pages 126 Through 204,'' July 15,
 2011.
``Response to NRC's Request for           ML13080A361
 Additional Information Regarding Rhode
 Island Nuclear Science Center Reactor
 License Renewal,'' March 15, 2013.
``Response to NRC's Request for           ML13080A362
 Additional Information Regarding Rhode
 Island Nuclear Science Center Reactor
 License Renewal,'' March 15, 2013.
``Response to NRC's Request for           ML13080A364
 Additional Information Regarding Rhode
 Island Nuclear Science Center Reactor
 License Renewal, Proposed Technical
 Specification 130314,'' March 15, 2013.
``Response to Request for Additional      ML13260A474
 Information Regarding Financial
 Qualifications for the RINSC Reactor
 License Renewal,'' September 16, 2013.
``Rhode Island Atomic Energy Commission   ML14006A420
 License Renewal Historical Resource
 Impact Response Letter,'' December 19,
 2013.
``Response to Request for Additional      ML14057A639
 Information Regarding Requalification
 Plan for the RINSC Reactor License
 Renewal,'' February 24, 2014.
``Compilation of All Submitted Requests   ML14126A192
 for Additional Information for the
 Rhode Island Nuclear Science Center
 Reactor License Renewal. Part 1 of 3,''
 April 28, 2014.
``Rhode Island Atomic Energy Commission   ML16279A523
 Consolidated Responses to Request for
 Additional Information Regarding
 License Renewal. Part 2 of 3
 (Redacted),'' April 28, 2014.
``Compilation of All Submitted Requests   ML14126A195
 for Additional Information for the
 Rhode Island Nuclear Science Center
 Reactor License Renewal. Part 3 of 3,''
 April 28, 2014.
``Rhode Island Nuclear Science Center     ML14184B361
 Reactor--Updated Proposed Technical
 Specifications,'' June 30, 2014.
``Rhode Island Nuclear Science Center     ML15223A953
 Updated Technical Specifications,''
 August 7, 2015.
``Rhode Island Nuclear Science Center     ML15223A952
 Submittal of Updated Proposed Technical
 Specification,'' August 11, 2015.
``Summary of Changes to the Proposed      ML15223A954
 Technical Specifications,'' August 11,
 2015.
``Contractor Comments and Responses,''    ML15223A955
 August 11, 2015.
``Rhode Island Nuclear Science Center     ML16062A378
 Transient Analyses Revised January 20,
 2016,'' January 20, 2016.
``Rhode Island Nuclear Science Center     ML16062A380
 Technical Specifications,'' February
 26, 2016.
``Rhode Island Atomic Energy Commission-- ML16062A373
 Response to Requests for Additional
 Information dated September 3, 2015,''
 March 1, 2016.
``Fuel Failure Addendum 160229,'' March   ML16062A381
 1, 2016.
``New Transient Analysis Results          ML16062A379
 160226,'' March 1, 2016.
``150903 RAI Responses 160301,'' March    ML16062A374
 1, 2016.

[[Page 1370]]

 
``Core Change Summary for Conversion      ML16062A375
 from RINSC LEU Core #5 to LEU Core
 #6,'' March 1, 2016.
``[RINSC] Fuel Failure Analysis [Dose     ML16062A382
 Table],'' March 1, 2016.
``Request for Change to License for the   ML16112A071
 Rhode Island Atomic Energy
 Commission,'' April 21, 2016.
``Rhode Island Atomic Energy Commission   ML16202A008
 Research Reactor--Responses to NRC
 Staff Request for Additional
 Information for License Renewal Review
 (Redacted Version),'' July 20, 2016.
``State of Rhode Island and Province      ML16280A420
 Plantations--Response to Request for
 Additional Dated August 3, 2016, Rhode
 Island Nuclear Science Center Response
 to NRC Request for Additional
 Information Regarding the Renewal, and
 Rhode Island Nuclear Science Center
 Technical Specifications,'' October 6,
 2016.
``State of Rhode Island and Providence    ML16306A063
 Plantations--Response to Request for
 Additional Information Regarding
 Calculations for Fuel Element Failure
 Accident Scenario,'' Letter and
 Responses, November 1, 2016.
``Rhode Island Atomic Energy Commission-- ML16319A298
 Transmittal of Supplemental Information
 in Support of Relicensing for the Rhode
 Island Nuclear Science Center (R-95),''
 Letter and Responses, November 14, 2016.
``Rhode Island Nuclear Science Center--   ML16336A734
 Supplemental Information for the
 Relicensing of the Rhode Island Atomic
 Energy Commission, Rhode Island Nuclear
 Science Center--Safety Analysis Report,
 and Rhode Island Nuclear Science
 Center--Technical Specifications,''
 December 1, 2016.
``State of Rhode Island and Province      ML16343A851
 Plantations--Supplemental Information
 Regarding Relicensing for the Rhode
 Island Nuclear Science Center,''
 December 8, 2016.
``Rhode Island December 13, 2016          ML16351A003
 Conversation Record,'' December 13,
 2016.
``Supplemental Information Re:            ML16350A042
 Relicensing for the Rhode Island
 Nuclear Science Center (R-95),''
 December 15, 2016.
``Rhode Island December 15 2016           ML16351A012
 Conversation Record,'' December 15,
 2016.
``Rhode Island Nuclear Science Center--   ML16350A256
 Supplemental Information Regarding
 Relicensing,'' December 15, 2016.
------------------------------------------------------------------------


    Dated at Rockville, Maryland, this 27th day of December 2016.

    For the Nuclear Regulatory Commission.
Steven T. Lynch,
Chief (Acting), Research and Test Reactors Branch, Division of Policy 
and Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. 2016-31980 Filed 1-4-17; 8:45 am]
 BILLING CODE 7590-01-P
Federal Register / Vol. 82, No. 3 / Thursday, January 5, 2017 / Notices 1365

outlet pressures, pressure differentials 28, and June 30, 2014; August 7 and gaseous effluent during normal reactor
and system flow rates. The licensee August 11, 2015; and January 20, operations.
conducts periodic tests of the secondary February 26, March 1, April 21, July 20, The licensee’s Technical
water for sodium-24 which would October 6, November 1, November 14, Specifications require that public doses
indicate a leak from the primary water December 1, December 8, December 13, from Ar–41 not exceed the 100 millirem
into the secondary water. and December 15, 2016 (collectively (mrem) annual public dose limit in 10
During normal operation of the RINSC referred to as ‘‘the renewal CFR 20.1301, ‘‘Dose limits for
reactor, the only significant airborne application’’). Initially, the operating individual members of the public.’’ The
radioactive effluent is Argon–41 (Ar– license was to expire at midnight on Ar–41 release rate would reach a
41). The primary liquid radioactive August 27, 2002, but a construction time maximum during continuous operation
effluents produced during normal recapture license amendment issued on at full power. Historical data shows that
operation include miscellaneous July 28, 2000 extended the license the reactor generates approximately 0.14
neutron activation products in the expiration date to July 21, 2004. Because ± 0.03 Curie (Ci) of Ar–41 per MW hour
primary coolant, many of which are of the timely renewal provision of operation. Using the Environmental
deposited in the mechanical filter and contained in 10 CFR 2.109(a), the Protection Agency COMPLY computer
demineralizer resins and, therefore, licensee is permitted to continue code, the licensee calculated the dose to
disposed of as solid radioactive waste. operation of the reactor under the terms the maximally-exposed member of the
Non-routine liquid radioactive wastes and conditions of its operating license public located 100 meters (328 feet)
can result from decontamination or until the license renewal application from the stack to be 0.021 mrem
maintenance activities, such as filter or before the NRC has been finally (0.00021 millisieverts (mSv)) per Ci of
resin replacements. Solid radioactive determined. The proposed renewal Ar–41 released. Using this result, the
wastes include waste generated from would authorize continued operation of licensee also calculated that an annual
reactor maintenance operations and the reactor for an additional 20 years release of 476 Ci of Ar–41
laboratory wastes from experiments. from the date of issuance of the renewed (corresponding to approximately 3,400
Much of the solid radioactive waste license. MW-hours, or 1,700 hours of operation
generated at the RINSC facility is held at full licensed power) from the RINSC
in a restricted area and allowed to decay Need for the Proposed Action reactor would correspond to a
to background levels and then disposed The proposed action is needed to maximum public dose of 10 mrem (0.10
of as non-radioactive waste. Solid allow the continued operation of the mSv) per year. The NRC staff finds the
radioactive waste that is not decayed in RINSC reactor to routinely provide licensee’s calculations to be reasonable
storage is transferred to a low-level teaching, research, and services to and conservative. Seven annual
waste broker for appropriate disposal. numerous institutions for a period of 20 operational reports covering the period
The RIAEC maintains a Radiation years from the date of issuance of the July 2009 through June 2016 (each
Protection Program, which involves renewed license. annual report covers a July through June
regular monitoring of airborne, liquid, reporting period) show that the
and solid gamma and beta radiation to Environmental Impacts of the Proposed maximum recorded release of Ar–41 in
ensure that any effluent releases are Action 1 year was 129.4 Ci, which would result
within the limits of 10 CFR part 20, The environmental impacts of the in a dose of 2.7 mrem (0.027 mSv) in 1
‘‘Standards For Protection Against proposed action are discussed below. As year to a member of the public. This is
Radiation.’’ The current environmental discussed below, the proposed action less than 3 percent of the 100 mrem (1
program consists of radiation area will not have a significant mSv) per year limit specified in 10 CFR
monitors (RAMs), continuous air environmental impact. In addition, the 20.1301. The maximum radiation dose
monitors (CAMs), portable radiation proposed action will not require any of 2.7 mrem (0.027 mSv) in 1 year also
survey instruments, personnel monitors, physical changes to the facility and the demonstrates compliance with the as
and stack gas and particulate monitors. impacts are similar to those occurring low as is reasonably achievable
Perimeter monitoring at the RINSC during past operations. (ALARA) air emissions dose constraint
facility consists of Optically-Stimulated of 10 mrem (0.10 mSv) specified in 10
Luminescent Dosimeters (OLDs) which A. Radiological Impacts CFR 20.1101, ‘‘Radiation protection
detect X-ray and gamma radiation. Environmental Effects of Reactor programs,’’ paragraph(d).
A detailed description of the reactor Operations Liquid radioactive wastes are
and its operations can be found in the produced as a result of normal operation
Safety Analysis Report (SAR) for the The only significant gaseous of the RINSC reactor, and typically
RINSC reactor submitted by RIAEC with radioactive effluent resulting from the consist of miscellaneous neutron
its renewal application. operation of the RINSC reactor is Ar–41. activation product impurities in the
This nuclide is released to the reactor coolant. Since most of these
Description of the Proposed Action environment from the reactor building activation products can be removed
The proposed action would renew from an exhaust stack on the roof that from the reactor coolant by collection on
Facility Operating License No. R–95 for combines the ventilation exhausts from the mechanical filters and the
a period of 20 years from the date of both the main and the purge systems. demineralizer resins, most of these
issuance of the renewed license. The The stack discharge length is 115 feet radioactive materials are typically
proposed action is in accordance with (35 meters). Nitrogen–16 (N–16) is also disposed as solid radioactive sources.
the licensee’s application dated May 3, produced during reactor operation, but While some non-routine liquid
mstockstill on DSK3G9T082PROD with NOTICES

2004, as supplemented on January 19, its release from the reactor stack is radioactive waste could be generated
February 4, August 6, August 18, insignificant because the half-life of N– due to decontamination or maintenance
September 3, September 8, November 16 is approximately 7 seconds and most activities, the amounts, based on a
26, December 7, and December 14, 2010; of the N–16 produced in the reactor review of the licensee’s past operating
January 24, February 24, and July 15, coolant would decay before reaching the experience, as reported in their annual
2011; March 15, September 16, and stack. Therefore Ar–41 is the most reports, have been and are expected to
December 19, 2013; February 24, April significant radionuclide released as a remain a small volume. Liquid

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1366 Federal Register / Vol. 82, No. 3 / Thursday, January 5, 2017 / Notices

radioactive wastes at the RINSC facility monitoring systems consist of RAMs, gaseous fission products in the
are allowed to decay in storage, are CAMs, portable radiation survey experiment are released into the air of
disposed of into the sanitary sewer in instruments, perimeter monitors, and the reactor building. From the reactor
accordance with 10 CFR 20.2003, stack gas and particulate monitors. The building, the release would continue to
‘‘Disposal by release into sanitary stack particulate and gas monitoring the environment. The licensee
sewerage,’’ or, when necessary, are systems measure the beta-gamma calculated doses to facility personnel
packaged and transported offsite for activity emitted by radioactive during a five minute evacuation
disposal. Annual operational reports particulates and the activity of gaseous duration, and also calculated the dose to
covering the period July 2009 through radioactive nuclides, respectively, that a member of the public outside the
June 2016 show that the licensee are exhausted through the RINSC facility during the two hours it would
complied with the limits on discharges facility stack. Perimeter monitoring at take the entire plume of released
to the sanitary sewer in 10 CFR part 20, RINSC facility consists of OLDs which radioactive material to pass. The
Appendix B. detect X-ray and gamma radiation. licensee estimated an occupational dose
Low-level solid radioactive waste The licensee conducts a monitoring of 1,570 mrem (15.7 mSv), and a dose
generated from reactor operations program to record and track the of 100 mrem (1 mSv) to the maximally-
typically includes laboratory wastes radiological impact of reactor operation exposed member of the public. The NRC
such as irradiated plastics, on the surrounding unrestricted area. staff reviewed the licensee’s
contaminated tools, towels, as well as The program consists of quarterly calculations, and found them to be
reactor demineralizer resins and exposure measurements at three generally reasonable and acceptable.
particulate filters. Any radioactive waste locations outside the reactor building The NRC staff also performed
that contains radionuclides with half- using OLDs. The licensee then applies independent calculations to verify that
lives of less than 90 days is allowed to an occupancy factor to determine the the licensee’s calculated doses
decay in storage and is then disposed of final exposure measurement. The represented conservative estimates for
as normal solid waste. Historically, one licensee’s radiation safety officer the MHA. The NRC staff estimated an
or two 55-gallon drums of solid waste administers the program and maintains occupational dose of 4,100 mrem (41.0
are generated each year, with the the appropriate records. Annual mSv), and a dose of 88 mrem (0.88 mSv)
activity being in the microcurie range. operational reports covering the period to the maximally-exposed member of
This waste is disposed of by a low-level July 2009 through June 2016 show that the public. The details of these
waste broker in accordance with all radiation exposures at the monitoring calculations are provided in the safety
applicable regulations for transportation locations were below the limits to the evaluation report that the NRC staff is
of radioactive materials. To comply with public as required by 10 CFR part 20. preparing to document the safety review
the Nuclear Waste Policy Act of 1982, Year-to-year trends in exposures are of the application for a renewed license.
the licensee has entered into a contract consistent between monitoring The NRC staff estimates that the
with the U.S. Department of Energy locations. Also, no correlation exists occupational radiation doses resulting
(DOE) that provides that DOE retains between total annual reactor operation from the postulated MHA would be
title to the fuel utilized at RINSC reactor and annual exposures measured at the below the 10 CFR 20.1201 limit of 5,000
and that DOE is obligated to take the monitoring locations. Based on review mrem (50 mSv). The NRC staff also
fuel from the site for final disposition. of data for the years 2009 through 2016, estimates that the maximum radiation
As described in Chapter 11 of the the NRC staff finds that operation of the doses for members of the public
RINSC reactor SAR, personnel RINSC reactor does not have any
resulting from the postulated MHA
exposures are well within the limits set significant radiological impact on the
would be at or below the 10 CFR
by 10 CFR 20.1201, ‘‘Occupational dose surrounding environment. No changes
limits for adults,’’ and are ALARA. The 20.1301 limit of 100 mrem (1 mSv).
in reactor operation that would affect
licensee tracks exposures of personnel off-site radiation levels are expected or The licensee has systems in place for
monitored with dosimeters, and proposed as a result of the proposed controlling the release of radiological
exposures are usually less than 10 action. effluents, and implements a radiation
percent of the occupational limit of Because occupational and public protection program to monitor
5,000 mrem (50 mSv) per year. Area exposures are below regulatory limits, personnel exposures and releases of
thermo-luminescent dosimeter monitors the NRC staff concludes that the radioactive effluents. The licensee’s
mounted in the control room and the proposed action would not have a systems and radiation protection
reactor bay provide an additional significant radiological impact. program are appropriate for the types
monthly measurement of total radiation and quantities of effluents expected to
Environmental Effects of Accidents be generated by continued operation of
exposures at those locations. Annual
operational reports covering the period Accident scenarios are discussed in the reactor. The NRC also staff evaluated
July 2009 through June 2016 show that Chapter 13 of the RINSC SAR. The information contained in the licensee’s
the personnel doses were well within accidents analyzed in Chapter 13 cover renewal application and data the
the 10 CFR 20.1201 limits. No changes a range of anticipated events, including licensee reported to the NRC for the last
in reactor operation that would lead to a postulated accident involving a fission 7 years of operation to determine the
an increase in occupational dose are product release with radiological projected radiological impact of the
expected or proposed as a result of the consequences that exceed those of any facility on the environment during the
proposed action. accident considered to be credible. This period of the renewed license. The NRC
The radiation monitoring systems limiting accident is referred to as the staff finds that releases of radioactive
mstockstill on DSK3G9T082PROD with NOTICES

associated with reactor operations at the maximum hypothetical accident (MHA). material and personnel exposures were
RINSC facility are provided and The licensee considers the uncontrolled all well within applicable regulatory
maintained as a means of ensuring release of the gaseous fission products limits. Because the licensee has not
compliance with radiation limits from a fissionable experiment to be the requested any changes to the facility
established under 10 CFR part 20, MHA. In the scenario used by the design or operating conditions as part of
‘‘Standards for Protection against licensee, an experiment containing the application for license renewal, the
Radiation.’’ The RINSC facility fissionable material fails, and the proposed action would not significantly

VerDate Sep<11>2014 21:06 Jan 04, 2017 Jkt 241001 PO 00000 Frm 00057 Fmt 4703 Sfmt 4703 E:\FR\FM\05JAN1.SGM 05JAN1
Federal Register / Vol. 82, No. 3 / Thursday, January 5, 2017 / Notices 1369

evaluation considered information documents. Accordingly, the NRC has related to the NRC’s FONSI. These
provided in the licensee’s application, determined not to prepare an documents are available for public
as supplemented, and the NRC staff’s environmental impact statement for the inspection online through ADAMS at
review of related environmental proposed action. http://www.nrc.gov/reading-rm/
documents. Section IV below lists the adams.html or in person at the NRC’s
IV. Availability of Documents
environmental documents related to the PDR as described previously.
proposed action and includes The following table identifies the
information on the availability of these references cited in this document and

ADAMS
Document accession No.

‘‘Rhode Island Atomic Energy Commission—‘Requesting Renewal of Operating License R–095 (Enclosure 2)’ [REDACTED ML14038A386
Safety Analysis Report],’’ May 3, 2004.
‘‘Rhode Island Atomic Energy Commission, Requesting Renewal of Operating License R–095,’’ May 3, 2004 ........................... ML041270519
‘‘Response to Request for Additional Information Concerning Plans for Decommissioning Facility at the End of Useful Life Ref ML100270176
Item 3 Parts a, b, and c,’’ January 19, 2010.
‘‘Rhode Island Nuclear Science Center, Appendix A to Safety Analysis Report, Information on Ar–41 and N–16,’’ (received ML16340A068
December 5, 2016), February 4, 2010.
‘‘Rhode Island Nuclear Science Center Reactor Submittal of Response to Request for Additional Information Re License Re- ML102240257
newal,’’ August 6, 2010.
‘‘Responding to Requests for Additional Information (RAI) regarding our Analysis of the Maximum Hypothetical Accident ML102360440
(MHA) for Renewal of License R–95,’’ August 18, 2010.
‘‘Memorandum Steady-State Thermal-Hydraulic Analysis for Forced-Convective Flow in the Rhode Island Nuclear Science ML16062A376
(RINSC) Reactor,’’ September 3, 2010.
‘‘Rhode Island Atomic Energy Commission, Fourth Response to Request for Additional Information dated April 23, 2010 (Re- ML16279A516
dacted),’’ September 8, 2010.
‘‘Rhode Island Atomic Energy Commission Fifth Response to April 13, 2010 Request for Additional Information (Regarding Li- ML16279A518
cense Renewal redacted),’’ November 26, 2010.
‘‘Rhode Island Atomic Energy Commission—Response to Requests for Additional Information Regarding Aging Issues Raised ML103490242
in RAIs,’’ December 7, 2010.
‘‘Rhode Island Atomic Energy Commission Response to April 13, 2010, Request for Additional Information Regarding License ML16279A519
Renewal Technical Specifications (Redacted),’’ December 14, 2010.
‘‘Reply to your Request for Additional Information (RAI) dated April 13, 2010, regarding License Renewal for the Rhode Island ML110320416
Nuclear Science Center Reactor (RINSC),’’ January 24, 2011.
‘‘Letter re: Request for Additional Information dated April 13, 2010 Regarding License Renewal for the Rhode Island Nuclear ML110600699
Science Center Reactor (RINSC),’’ February 24, 2011.
‘‘Rhode Island Atomic Energy Commission Response to Request for Additional Information Regarding License Renewal,’’ July ML11202A287
15, 2011.
‘‘Rhode Island Atomic Energy Commission Tenth Response to the April 13, 2010, Request for Additional Information Regard- ML16279A520
ing License Renewal (Redacted),’’ July 15, 2011.
‘‘Rhode Island Atomic Energy Commission Responses to Request for Additional Information Regarding License Renewal (Re- ML16279A521
dacted),’’ July 15, 2011.
‘‘Rhode Island Nuclear Science Center Tenth Response to NRC Request for Additional Information dated April 13, 2010, ML11202A290
Pages 126 Through 204,’’ July 15, 2011.
‘‘Response to NRC’s Request for Additional Information Regarding Rhode Island Nuclear Science Center Reactor License ML13080A361
Renewal,’’ March 15, 2013.
‘‘Response to NRC’s Request for Additional Information Regarding Rhode Island Nuclear Science Center Reactor License ML13080A362
Renewal,’’ March 15, 2013.
‘‘Response to NRC’s Request for Additional Information Regarding Rhode Island Nuclear Science Center Reactor License ML13080A364
Renewal, Proposed Technical Specification 130314,’’ March 15, 2013.
‘‘Response to Request for Additional Information Regarding Financial Qualifications for the RINSC Reactor License Renewal,’’ ML13260A474
September 16, 2013.
‘‘Rhode Island Atomic Energy Commission License Renewal Historical Resource Impact Response Letter,’’ December 19, ML14006A420
2013.
‘‘Response to Request for Additional Information Regarding Requalification Plan for the RINSC Reactor License Renewal,’’ ML14057A639
February 24, 2014.
‘‘Compilation of All Submitted Requests for Additional Information for the Rhode Island Nuclear Science Center Reactor Li- ML14126A192
cense Renewal. Part 1 of 3,’’ April 28, 2014.
‘‘Rhode Island Atomic Energy Commission Consolidated Responses to Request for Additional Information Regarding License ML16279A523
Renewal. Part 2 of 3 (Redacted),’’ April 28, 2014.
‘‘Compilation of All Submitted Requests for Additional Information for the Rhode Island Nuclear Science Center Reactor Li- ML14126A195
cense Renewal. Part 3 of 3,’’ April 28, 2014.
‘‘Rhode Island Nuclear Science Center Reactor—Updated Proposed Technical Specifications,’’ June 30, 2014 ......................... ML14184B361
‘‘Rhode Island Nuclear Science Center Updated Technical Specifications,’’ August 7, 2015 ........................................................ ML15223A953
‘‘Rhode Island Nuclear Science Center Submittal of Updated Proposed Technical Specification,’’ August 11, 2015 ................... ML15223A952
‘‘Summary of Changes to the Proposed Technical Specifications,’’ August 11, 2015 .................................................................... ML15223A954
mstockstill on DSK3G9T082PROD with NOTICES

‘‘Contractor Comments and Responses,’’ August 11, 2015 ............................................................................................................ ML15223A955
‘‘Rhode Island Nuclear Science Center Transient Analyses Revised January 20, 2016,’’ January 20, 2016 ................................ ML16062A378
‘‘Rhode Island Nuclear Science Center Technical Specifications,’’ February 26, 2016 .................................................................. ML16062A380
‘‘Rhode Island Atomic Energy Commission—Response to Requests for Additional Information dated September 3, 2015,’’ ML16062A373
March 1, 2016.
‘‘Fuel Failure Addendum 160229,’’ March 1, 2016 .......................................................................................................................... ML16062A381
‘‘New Transient Analysis Results 160226,’’ March 1, 2016 ............................................................................................................. ML16062A379
‘‘150903 RAI Responses 160301,’’ March 1, 2016 .......................................................................................................................... ML16062A374

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Document Created: 2018-02-01 14:50:48
Document Modified: 2018-02-01 14:50:48
Category		Regulatory Information
Collection		Federal Register
sudoc Class		AE 2.7: GS 4.107: AE 2.106:
Publisher		Office of the Federal Register, National Archives and Records Administration
Section		Notices
Action		Environmental assessment and finding of no significant impact; issuance.
Dates		The EA and FONSI are available on January 5, 2017.
Contact		Patrick G. Boyle, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Rockville, MD 20852. Telephone: 301-415-3936; email: [email protected]
FR Citation		82 FR 1364