[Federal Register Volume 75, Number 191 (Monday, October 4, 2010)]
[Notices]
[Pages 61220-61225]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2010-24809]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-020; NRC-2010-0313]
Massachusetts Institute of Technology: Massachusetts Institute of
Technology Research Reactor Environmental Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory Commission (NRC, the Commission) is
considering issuance of a renewed Facility Operating License No. R-37,
to be held by the Massachusetts Institute of Technology (MIT, the
licensee), which would authorize continued operation of the
Massachusetts Institute of Technology Research Reactor (MITR-II, the
facility), located in Cambridge, Middlesex County, Massachusetts.
Therefore, as required by Title 10 of the Code of Federal Regulations
(10 CFR) 51.21, the NRC is issuing this Environmental Assessment (EA)
and Finding of No Significant Impact.
[[Page 61221]]
Environmental Assessment
Identification of the Proposed Action
The proposed action would renew Facility Operating License No. R-37
for a period of twenty years from the date of issuance of the renewed
license and increase the maximum licensed power level from 5 megawatts
thermal (MW(t)) to 6 MW(t). The proposed action is in accordance with
the licensee's application dated July 8, 1999, as supplemented by
letters dated February 10 and May 8, 2000, January 29, 2004, July 5 and
October 11, 2006, January 26, 2007, February 22, May 29, August 15,
August 21, August 26, October 6, October 7 and December 1, 2008, May
26, August 27, October 5, October 9 and November 19, 2009, and March
30, August 6 and August 26, 2010. 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 MITR-II to routinely provide teaching, research, and services to
numerous institutions for a period of twenty years. The proposed action
is also needed to enhance the facility's experiment capabilities by
increasing the maximum neutron flux in the experiment facilities.
Environmental Impacts of the Proposed Action
The NRC staff has completed its safety evaluation of the proposed
action to issue a renewed Facility Operating License No. R-37 to allow
continued operation of the MITR for a period of twenty years at an
increased power level of 6 MW(t) and concludes there is reasonable
assurance that the MITR-II will continue to operate safely for the
additional period of time at the increased licensed power level. The
details of the NRC staff's safety evaluation will be provided with the
renewed license that will be issued as part of the letter to the
licensee approving the license renewal application. This document
contains the environmental assessment of the proposed action.
The MITR-II is located on the MIT campus and is a part of the MIT
Nuclear Reactor Laboratory. The reactor is housed in a dedicated
building constructed primarily of reinforced concrete and steel which
serves as a containment. The reactor site comprises the reactor
building and a small area immediately surrounding it, bounded by a
chain-link fence, and a portion of an attached multipurpose academic
building. Adjacent to the site are an industrial building to the north,
a parking lot and warehouse building to the east, a warehouse building
to the south, and academic and dormitory buildings to the west.
According to the licensee, the nearest point of normal public occupancy
is on Albany Street, approximately 21 meters (68 feet) northwest of the
reactor building, the nearest dormitories are located approximately 100
meters (330 feet) west of the reactor, and the nearest non-MIT
residence is approximately 250 meters (820 feet) from the reactor
building.
The MITR-II is a tank-type, light-water-cooled and heavy-water-
moderated research reactor that will be licensed to operate at a
maximum steady-state power level of 6 MW(t). The core is located at the
bottom of an aluminum tank surrounded by a heavy water reflector tank
and a concrete biological shield. The reactor is fueled with plate-
type, aluminum-clad fuel arranged in a compact core. A detailed
description of the reactor can be found in the MITR-II Safety Analysis
Report (SAR).
There have been no major modifications to the Facility Operating
License since Amendment No. 10, dated July 23, 1975, which approved
operation of a modified reactor core at a maximum power level of 5
MW(t). In connection with Amendment No. 10, the NRC staff evaluated the
potential for environmental impacts associated with operation of the
MITR-II. Based on that evaluation, the NRC staff concluded that there
would be no significant environmental impact associated with licensing
the MITR-II to operate at a maximum power level of 5 MW(t).
The licensee requested a change in the facility operating
conditions as part of the renewal request. Specifically, the licensee
requested an increase in the licensed maximum steady-state power level.
This change should not affect the types of effluents released off site.
There may be an increase in the quantity of gaseous effluents released
offsite due to the increase in maximum power level. As discussed in
this EA, off site concentrations of airborne radioactive material and
potential radiation doses should continue to be a small fraction of the
limits established in 10 CFR Part 20. 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. As discussed in the NRC staff's
safety evaluation, the systems and radiation protection program are
appropriate for the types and quantities of effluents expected to be
generated by continued operation of the reactor at the increased power
level. Accordingly, there should be no significant increase in routine
occupational or public radiation exposure as a result of license
renewal or the increase in maximum power level. As discussed in the NRC
staff's safety evaluation, the proposed action will not significantly
increase the probability of accidents. The proposed action may increase
the consequences of accidents. Specifically, the increase in maximum
steady-state power level may increase the fission product source term
and potential occupational and public accident doses for the maximum
hypothetical accident. As discussed in the NRC staff's safety
evaluation, the worst case fission product source term will not result
in occupational doses or doses to members of the general public in
excess of the limits specified by 10 CFR part 20. Therefore, the
proposed action should not significantly change the environmental
impact of facility operation. The NRC staff evaluated information
contained in the licensee's application and data reported to the NRC by
the licensee for the last five years of operation to determine the
projected radiological impact of the facility on the environment during
the period of the renewed license at the increased power level. 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 and the increase in the licensed maximum steady-state power
level should not have a significant environmental impact.
I. Radiological Impact
Environmental Effects of Reactor Operations
Gaseous radioactive effluents are discharged by the facility
exhaust system via a stack adjacent to the reactor building, at a
volumetric flow rate of approximately 3.5 cubic meters per second
(7,500 cubic feet per second). The only significant nuclide found in
the gaseous effluent stream is Argon-41. The licensee performs
continuous measurements of Argon-41 at the point of release. Argon-41
releases reported in the licensee's annual reports average
approximately 1445 Curies (Ci) for a typical year. According to the
licensee's annual reports, these releases resulted in an annual average
effluent concentration of 0.386E-8 microCuries per milliliter (mCi/ml).
The NRC staff performed check calculations of Argon-
[[Page 61222]]
41 releases and found the licensee's calculations to be reasonable. The
calculated value is based on a dilution factor of 3,000 for gaseous
effluents released from the facility exhaust stack. The licensee's
application for license renewal contains a more realistic, and still
conservative, dilution factor of 50,000. Based on this dilution factor,
the annual average effluent concentration of Argon-41 would be 0.023E-8
[mnplus]Ci/ml. This concentration is less than three percent of the air
effluent concentration limit of 1E-8 [mnplus]Ci/ml set by 10 CFR part
20, appendix B, Table 2. The potential annual radiation dose to a
member of the general public resulting from this concentration is
approximately 0.012 milliSieverts (mSv) (1.2 millirems (mrem)). As
discussed later in this EA, the licensee's off-site dose measurements
show a potential annual radiation dose from gaseous effluents of less
than 0.01 mSv (1 mrem). These potential radiation doses demonstrate
compliance with the dose limit of 1 mSv (100 mrem) set by 10 CFR
20.1301, and the air emissions dose constraint of 0.1 mSv (10 mrem)
specified in 10 CFR 20.1101(d). The increase in maximum steady-state
power level may increase the production of Argon-41 by 20 percent.
Calculations by the licensee predict a maximum potential annual
radiation dose to a member of the public of less than 0.02 mSv (2 mrem)
given a 20 percent increase in Argon-41 production. The NRC staff
performed check calculations of the maximum potential dose and found
the licensee's calculations to be reasonable. The calculated potential
dose is a small fraction of the regulatory limits discussed above.
Because the licensee performs continuous monitoring of all airborne
releases, the effluent concentrations at the increased power level will
be measured to ensure that releases remain below the regulatory limits
and as low as is reasonably achievable (ALARA).
Liquid wastes are generated at the MITR-II primarily as a result of
sampling of the coolant, decontamination activities, and routine
cleaning of the facility. Liquid wastes are stored in two above-ground
tanks located in a dedicated structure equipped with leak detection and
leak containment capabilities. The licensee disposes of liquid
radioactive wastes primarily by discharge to the sanitary sewer. Liquid
wastes may also be disposed of by use of ion exchangers, decay in
storage, solidification, or transfer to an appropriate waste management
facility. Discharge of liquid waste to the sanitary sewer requires the
approval of the Reactor Radiation Protection Office (RRPO) to ensure
that discharges meet the requirements of 10 CFR 2.2003. Prior to
discharge, a waste sample is analyzed for gross alpha-beta, tritium,
and isotopic content to ensure the concentrations of radionuclides in
the liquid meet the limits in 10 CFR Part 20, Appendix B, Table 3 for
releases to sewers. A sewer discharge pump is located within the
restricted area for the discharge of liquid waste to the sewer system.
The discharge path is from the liquid waste storage tanks into a
filtration system, through a radiation monitor for continuous
monitoring, and then to the sewer. Discharges reported in the
licensee's annual reports indicate an annual average release of 0.08
milliCuries (mCi) of radionuclides other than tritium. Reported annual
releases have not exceeded 0.21 mCi. This demonstrates compliance with
the annual release limit of 1 Ci specified in 10 CFR 20.2003(a)(4) for
radionuclides other than tritium. These radionuclides were discharged
at an annual average concentration of 0.54E-8 [mnplus]Ci/ml, with no
monthly average concentration exceeding 9.3E-8 [mnplus]Ci/ml. As
mentioned above, the licensee performs appropriate sampling to ensure
releases of liquid mixtures of radionuclides meet the release criteria
in 10 CFR 20.2003. Tritium discharges reported in the licensee's annual
reports indicate an annual average release of 240 milliCuries (mCi) at
an average concentration of 1.91E-5 [mnplus]Ci/ml. The maximum monthly
concentration released during the past 5 years was 2.19E-4 [mnplus]Ci/
ml. These releases demonstrate compliance with the annual limit of 5 Ci
specified in 10 CFR 20.2003(a)(4) and the monthly average concentration
limit of 1.0E-2 [mnplus]Ci/ml for disposal of tritium by releases to
sewers specified in 10 CFR 20, Appendix B, Table 3. Due to the nature
of the liquid waste sources, quantities of liquid wastes should not
increase significantly as a result of the increase in maximum steady-
state power level. Because the licensee samples all liquid wastes prior
to discharge and continuously monitors the wastes during discharge, the
licensee's liquid waste discharge program is adequate to ensure that
all releases will remain within the applicable regulatory limits.
The licensee classifies solid low-level radioactive wastes
generated at the MITR-II as either wet or dry waste. Wet waste includes
filters and ion exchange resins. Dry waste includes ventilation filters
and contaminated materials such as paper, cloth, metals, and other
items used for routine facility operations. Solid waste may also
include reactor components and experiment materials. Solid waste
management is divided into four processes: Collection, pretreatment,
solidification, and packing. According to the licensee, volume
reduction methodologies are applied to all processes and solid wastes
are stored onsite for decay. After solid waste is processed, it is sent
to a designated waste facility in accordance with all applicable
regulations. Solid radioactive releases reported in the licensee's
annual reports for the last 5 years totaled 1127 mCi.
The reactor fuel and heavy-water are supplied by the Department of
Energy (DOE). The DOE is responsible for disposing of the spent fuel
and the heavy-water. To comply with the Nuclear Waste Policy Act of
1982, MIT has entered into a contract with DOE that provides that DOE
retain title to the fuel utilized at the MITR-II and that DOE is
obligated to take the fuel from the site for final disposition. The
licensee prepares the spent fuel for shipment in accordance with the
applicable regulations in 10 CFR parts 71 and 73, and U.S. Department
of Transportation regulations. Heavy-water is likewise treated and
stored in the facility until DOE transfers it to a DOE storage facility
or to a processing facility.
Personnel exposures at the facility are well within the limits set
by 10 CFR 20.1201, and ALARA. Doses to personnel are monitored under a
program that meets the requirements of 10 CFR 20.1501. The RRPO records
and tracks all personnel radiation exposures. Data reported in the
licensee's annual reports indicates that most personnel receive an
annual dose of less than 1 mSv (100 mrem), with many of the personnel
doses being below the detectable level. Data reported in the licensee's
annual reports indicates that the maximum personnel dose is typically
less than 7.5 mSv (750 mrem) per year, and no personnel have received a
dose greater than half the occupational limit of 50 mSv (5,000 mrem)
specified in 10 CFR 20.1201. The licensee maintains air sampling, area
radiation monitoring, and bioassay programs to further monitor
potential radiation hazards and exposures to personnel. The licensee
does not expect the increase in reactor power level to cause a
proportional increase in personnel doses. However, even with a 20
percent increase, personnel doses will remain well below the regulatory
limit and the licensee's radiation protection program should continue
to keep personnel doses ALARA.
[[Page 61223]]
The licensee conducts an environmental monitoring program to record
and track the potential radiological impact of MITR-II operation on the
surrounding environment. The RRPO administers the program and maintains
the appropriate records in accordance with 10 CFR 20.2103. The program
includes monthly exposure measurements at locations on the restricted
area boundary and control locations. The program also includes
quarterly exposure measurements and continuous monitoring using Geiger-
Mueller tube detectors at five locations approximately 0.40 kilometers
(0.25 miles) from the site boundary. The measurements are
representative of potential public radiation doses from the release of
gaseous effluents from the facility. Over the past five years, the
environmental monitoring program indicated that radiation exposures at
the monitoring locations were less than 0.01 mSv (1 mrem) per year.
Based on the NRC staff's review of the past five years of data, the NRC
staff concludes that the potential radiological impact of operation of
the MITR-II on the surrounding environment is a small fraction of the
regulatory limits. Any changes in radiological impact due to the
increase in reactor power are expected to be minimal, and the potential
radiological impact will remain a small fraction of the regulatory
limits.
Environmental Effects of Accidents
Accident scenarios are discussed in Chapter 13 of the MITR-II SAR.
The maximum hypothetical accident is the release of the fission
products contained in four fuel plates to the reactor coolant, the
containment building, and ultimately the uncontrolled environment. The
licensee conservatively calculated doses to facility personnel and the
maximum potential dose to a member of the public. NRC staff performed
independent calculations to verify that the doses represent
conservative estimates for the MHA. As discussed in the NRC staff's
safety evaluation, the worst case fission product source term will not
result in occupational doses or doses to members of the general public
in excess of the limits specified by 10 CFR part 20.
II. Non-Radiological Impacts
The MITR-II core is cooled by a light water primary system
consisting of the reactor tank, a heat removal system, and a coolant
cleanup system. Cooling occurs by forced or natural convection, with
the heated coolant rising out of the core and into the bulk tank water.
The primary system transfers heat to the secondary system via heat
exchangers. The secondary system also contains heat exchangers to
remove heat from other reactor systems at the MITR-II. The secondary
system coolant is continuously monitored for radioactivity using
redundant radiation detectors, and the coolant is sampled for
radioactivity daily during reactor operation.
Losses of secondary coolant due to evaporation and system discharge
to the sewer (blowdown) are replaced using water from the local city
water supply. According to the licensee, daily secondary coolant losses
are approximately 7,000 gallons due to system blowdown and an average
of 30,000 gallons due to evaporation during reactor operation. This is
a small percentage of the approximate 2.7 million gallons used campus-
wide by MIT per day. The increase in licensed power level may
proportionally increase the facility water usage, but the total
facility water usage will remain a small percentage of the campus-wide
water usage. Given that the proposed action does not involve a
significant increase in water usage, the NRC staff concludes that the
proposed action will not have a significant impact on the local water
supply.
Heat is transferred from the secondary system to the atmosphere via
cooling towers rated at 10 MW(t) total heat dissipation capacity.
During reactor operation at 6 MW(t), the heat dissipation would be
comparable to that at local factories and other MIT laboratories.
Neither extensive heat drift nor fog will occur at this heat
dissipation rate. A small amount of heat may be discharged to the sewer
during blowdown of the cooling towers. However, the small amount of
heat dissipated in this manner is insufficient to raise average water
temperatures in the surrounding environment. Based on the above
considerations, the NRC staff concludes that the proposed action will
not have a significant thermal impact on the surrounding environment.
National Environmental Policy Act (NEPA) Considerations
NRC has responsibilities that are derived from NEPA and from other
environmental laws, which include the Endangered Species Act (ESA),
Coastal Zone Management Act (CZMA), National Historic Preservation Act
(NHPA), Fish and Wildlife Coordination Act (FWCA), and Executive Order
12898 Environmental Justice. The following presents a brief discussion
of impacts associated with these laws and other requirements.
I. Endangered Species Act
Federally- or State-protected species have not been found in the
vicinity of the MITR-II. Effluents and emissions from the MITR-II have
not had an impact on critical habitat.
II. Coastal Zone Management Act
The MITR-II is not located within any managed coastal zones, nor
would the MITR-II effluents and emissions impact any managed coastal
zones.
III. National Historic Preservation Act
The NHPA requires Federal agencies to consider the effects of their
undertakings on historic properties. The National Register of Historic
Places (NRHP) lists two historical sites located near the MIT campus,
the North Avenue Congregational Church and the New England
Confectionery Company Factory. According to the NRHP, the locations of
these sites are approximately 100 meters (300 feet) from the MITR-II.
Given the distance to these sites and that the proposed action does not
involve any demolition, rehabilitation, construction, changes in land
use, or significant changes in effluents from the facility, continued
operation of the MITR-II will not impact any historic sites. Based on
this information, the NRC finds that the potential impacts of license
renewal would have no adverse effect on historic properties. The NRC
staff informed the State Historic Preservation Officer (SHPO) of this
finding, and the SHPO concurred with the NRC finding.
IV. Fish and Wildlife Coordination Act
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.
V. 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 MITR-II. Such
effects may include human health, biological, cultural, economic, or
social impacts. Minority and low-income populations are subsets of the
general public residing in the vicinity of the research reactor, and
all are exposed to the same health and environmental effects
[[Page 61224]]
generated from activities at the MITR-II.
Minority Populations in the Vicinity of the MITR-II--According to
2000 census data, 18.1 percent of the population (approximately
6,472,000 individuals) residing within a 50-mile radius of the MITR-II
identified themselves as minority individuals. The largest minority
group was Hispanic or Latino (approximately 438,000 persons or 6.8
percent), followed by Black or African American (approximately 397,000
persons or about 6.1 percent). According to the U.S. Census Bureau,
about 16.4 percent of the Middlesex County population identified
themselves as minorities, with persons of Asian origin comprising the
largest minority group (6.9 percent). According to census data 3-year
average estimates for 2006-2008, the minority population of Middlesex
County, as a percent of total population, had increased to 20.1
percent.
Low-Income Populations in the Vicinity of the MITR-II--According to
2000 census data, approximately 106,300 families and 575,000
individuals (6.6 and 8.9 percent, respectively) residing within a 50-
mile radius of the MITR-II were identified as living below the Federal
poverty threshold in 1999. The 1999 Federal poverty threshold was
$17,029 for a family of four.
According to Census data in the 2006-2008 American Community Survey
3-Year Estimates, the median household income for Massachusetts was
$64,684, while 10.0 percent of the state population and 7.1 percent of
families were determined to be living below the Federal poverty
threshold. Middlesex County had a higher median household income
average ($77,373) and lower percentages (7.4 percent) of individuals
and families (4.9 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 near 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 EA, 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 MITR-II.
Environmental Impacts of the Alternatives to the Proposed Action
As an alternative to license renewal, the NRC staff considered
denial of the proposed action. If the Commission denied the application
for license renewal, facility operations would end and decommissioning
would be required. The NRC staff notes that, even with a renewed
license, the MITR-II will eventually be decommissioning, at which time
the environmental effects of decommissioning will 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 reactor 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 MITR-II. If the Commission denied the
request for an increase in the licensed maximum steady-state power
level, effluent releases and emissions would remain at the current
levels. As discussed in this EA, the increase in power level should not
result in a significant increase in effluent releases, and all releases
will remain a small fraction of the applicable regulatory limits.
Therefore, the environmental impacts of the increase in the licensed
maximum steady-state power level and denial of the request are similar.
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-37 for the MITR-II dated July 23, 1975, which
approved operation of a modified reactor core at a maximum power level
of 5 MW(t).
Agencies and Persons Consulted
In accordance with the agency's stated policy, on July 22, 2010,
the NRC staff consulted with the State Liaison Officer regarding the
environmental impact of the proposed action. The consultation involved
a thorough explanation of the environmental review, the details of this
environmental assessment, and the NRC staff's findings. The State
official stated the he understood the NRC review and had no comments
regarding the proposed action. The NRC staff also informed the SHPO of
the potential impact of the proposed action on historic resources. As
previously mentioned, the SHPO concurred with the NRC determination
that license renewal and the increase in licensed power level would
have no adverse effect on historic properties in the vicinity of the
MITR-II.
Finding of No Significant Impact
On the basis of the environmental assessment, the NRC concludes
that the proposed action will not have a significant effect on the
quality of the human environment. Accordingly, the NRC has determined
not to prepare an environmental impact statement for the proposed
action.
For further details with respect to the proposed action, see the
licensee's letter dated July 8, 1999 (ML080950435), as supplemented by
letters dated February 10 (ML003683419, ML052900533, ML053190234, and
ML053190384), and May 8, 2000 (ML081000625), January 29, 2004
(ML081000626), July 5 (ML061930319) and October 11, 2006 (ML063340716),
January 26, 2007 (ML070320555), February 22 (ML081000627), May 29
(ML081560246), August 15 (ML082350069), August 21 (ML082401050), August
26 (ML082470562), October 6 (ML082900488), October 7 (ML082910241), and
December 1, 2008 (ML083430006), May 26 (ML091540202), August 27
(ML092450427), October 5 (ML092930273), October 9 (ML092930278), and
November 19, 2009 (ML093290155), and March 30 (ML100970368), August 6
(ML102310032), and August 26, 2010 (ML102440122). Documents may be
examined, and/or copied for a fee, at the NRC's Public Document Room
(PDR), located at One White Flint North, 11555 Rockville Pike (first
floor), Rockville, Maryland. Publicly available records will be
accessible electronically from the Agencywide Documents Access and
Management System (ADAMS) Public Electronic Reading Room on the NRC Web
site http://www.nrc.gov/reading-rm/adams.html. Persons who do not have
access to ADAMS or who encounter problems in accessing the documents
located in ADAMS should contact the NRC PDR Reference staff at 1-800-
397-4209, or 301-415-4737, or send an e-mail to [email protected].
[[Page 61225]]
Dated at Rockville, Maryland, this 27th day of September 2010.
For the Nuclear Regulatory Commission.
Jessie Quichocho,
Chief, Research and Test Reactors Licensing Branch, Division of Policy
and Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. 2010-24809 Filed 10-1-10; 8:45 am]
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