[Federal Register Volume 74, Number 217 (Thursday, November 12, 2009)]
[Notices]
[Pages 58319-58322]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E9-27282]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-005; NRC-2009-0495]
Pennsylvania State University: Penn State Breazeale Reactor;
Environmental Assessment and Finding of No Significant Impact
The U.S. Nuclear Regulatory Commission (NRC or the Commission) is
considering issuance of a renewed Facility Operating License No. R-2,
to be held by Pennsylvania State University (PSU or the licensee),
which would authorize continued operation of the Penn State Breazeale
Reactor (PSBR), located in University Park, Centre County,
Pennsylvania. Therefore, as required by Title 10 of the Code of Federal
Regulations (10 CFR) Section 51.21, the NRC is issuing this
Environmental Assessment and Finding of No Significant Impact.
Environmental Assessment
Identification of the Proposed Action
The proposed action would renew Facility Operating License No. R-2
for a period of twenty years from the date of issuance of the renewed
license. The proposed action is in accordance with the licensee's
application dated December 6, 2005, as supplemented by letters dated
October 31, 2008, and April 2, June 11, September 1, and October 21,
2009. 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 PSBR to routinely provide teaching, research, and services to
numerous institutions for a period of twenty years.
Environmental Impacts of the Proposed Action
The NRC has completed its safety evaluation of the proposed action
to issue a renewed Facility Operating License No. R-2 to allow
continued operation of the PSBR for a period of twenty years and
concludes there is reasonable assurance that the PSBR will continue to
operate safely for the additional period of time. The details of the
NRC staff's safety evaluation will be
[[Page 58320]]
provided with the renewed license that will be issued as part of the
letter to the licensee approving its license renewal application. This
document contains the environmental assessment of the proposed action.
The PSBR is located on the main campus of PSU and is a part of the
Radiation Science and Engineering Center. The reactor is housed in a
multipurpose building constructed primarily of concrete, brick, steel,
and aluminum which serves as a confinement. The reactor site comprises
the reactor building and a small area immediately surrounding it,
bounded by a chain-link fence. Adjacent to the site are athletic
facilities to the north and west, fields and parking lots to the east,
and academic and research buildings to the south. The nearest permanent
residences are located approximately 360 meters (390 yards) from the
site boundary. The nearest dormitories are located approximately 130
meters (120 yards) south of the reactor.
The PSBR is a pool-type, light water moderated and cooled research
reactor licensed to operate at a steady-state power level of 1 megawatt
thermal power (MW(t)). The reactor is also licensed to operate in a
pulse mode. The fuel is located at the bottom of a polyurea-lined
concrete pool with a volume of approximately 270,000 liters (71,000
gallons) and a depth of 7.3 meters (24 feet). The reactor is fueled
with standard low-enriched uranium TRIGA fuel. A detailed description
of the reactor can be found in the PSBR Safety Analysis Report (SAR).
There have been no major modifications to the Facility Operating
License since renewal of the license on January 27, 1986.
The licensee has not requested any changes to the facility design
or operating conditions as part of the application for license renewal.
No changes are being made in the types or quantities of effluents that
may be released off site. 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. Accordingly, there
should be no increase in routine occupational or public radiation
exposure as a result of license renewal. As discussed in the NRC
staff's safety evaluation, the proposed action will not significantly
increase the probability or consequences of accidents. Therefore,
license renewal should not change the environmental impact of facility
operation. The NRC staff evaluated information contained in the
licensee's application and data reported to the NRC by the licensee for
the last five years of operation to determine the projected
radiological impact of the facility on the environment during the
period of the renewed license. The NRC staff found that releases of
radioactive material and personnel exposures were all well within
applicable regulatory limits. Based on this evaluation, the NRC staff
concluded that continued operation of the reactor 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 vents located on the roof of the reactor building,
at a volumetric flow rate of approximately 1.4 cubic meters per second
(3000 cubic feet per second). Other release pathways do exist, however
they are normally secured during reactor operation and have
insignificant volumetric flow rates compared to the facility exhaust
system. The only significant nuclide found in the gaseous effluent
stream is Argon-41. The licensee performed measurements of Argon-41
production for conditions of low-power and high-power reactor
operation. Licensee calculations, based on those measurements, indicate
that annual Argon-41 releases result in an offsite concentration of
3.2E-10 microCuries per milliliter (mCi/ml), which is below
the limit of 1.0E-8 mCi/ml specified in 10 CFR 20, Appendix
B for air effluent releases. The NRC staff performed an independent
calculation and found the licensee's calculation to be reasonable. The
licensee also performed measurements and calculations to estimate the
potential release of tritium resulting from evaporation of the reactor
pool water. The NRC staff performed independent calculations and found
the licensee's calculations to be reasonable and the potential airborne
tritium concentration to be a small fraction of the air effluent
concentration limit specified in 10 CFR 20, Appendix B. Total gaseous
radioactive releases reported to the NRC in the licensee's annual
reports were less than four percent of the air effluent concentration
limits set by 10 CFR 20, Appendix B. The potential radiation dose to a
member of the general public resulting from this concentration is
approximately 0.02 milliSieverts (mSv) (2 millirems (mrem)) and this
demonstrates compliance with the dose limit of 1 mSv (100 mrem) set by
10 CFR 20.1301. Additionally, this potential radiation dose
demonstrates compliance with the air emissions dose constraint of 0.1
mSv (10 mrem) specified in 10 CFR 20.1101(d).
The licensee disposes of liquid radioactive wastes by evaporation,
discharge to the sanitary sewer, or transfer to the Radiation
Protection Office (RPO) which is a part of the PSU Department of
Environmental Health and Safety. Disposal by evaporation removes the
liquid from the liquid radioactive waste, creating demineralized water
and traces of solid radioactive waste that remain in the evaporator
tank for decay. Discharge of liquid waste to the sanitary sewer
requires the use of procedures and RPO approval to ensure that
discharges meet the requirements of 10 CFR 20.2003 for disposal by
release into sanitary sewerage. The licensee also transfers small
quantities of liquid radioactive waste to the RPO for proper disposal
under the University's broad scope byproduct material license. During
the past five years, the licensee reported no routine releases of
liquid radioactive waste by any of the disposal methods. One unplanned
release occurred as a result of leakage of reactor pool water through
the reactor pool liner to the earthen backfill surrounding the reactor
pool. According to the licensee, the leakage resulted in the release of
approximately 1.3 milliCuries of tritium, at a concentration of 2.8E-5
Ci/ml. This concentration is a fraction of the limit of 1E-
3 Ci/ml specified in 10 CFR Part 20, Appendix B for liquid
effluents. Offsite groundwater sampling conducted by the licensee
showed no detectable elevation in tritium levels. The NRC inspection
report related to the reactor pool leakage identified no findings of
significance.
The RPO oversees the handling of solid low-level radioactive waste
generated at the PSBR. The bulk of the waste consists of gloves, paper,
plastic, and small pieces of metal. Upon removal from the facility by
the RPO, the waste enters the campus-wide radioactive waste stream
covered by the University's broad scope byproduct material license. The
RPO disposes of the waste by decay in storage or shipment to a low
level waste broker in accordance with all applicable regulations for
transportation of radioactive materials. According to the licensee, no
spent nuclear fuel has been shipped from the site to date. To comply
with the Nuclear Waste Policy Act of
[[Page 58321]]
1982, PSU has entered into a contract with the U.S. Department of
Energy (DOE) that provides that DOE retains title to the fuel utilized
at the PSBR and that DOE is obligated to take the fuel from the site
for final disposition.
As described in Chapter 11 of the PSBR SAR, personnel exposures are
well within the limits set by 10 CFR 20.1201, and as low as is
reasonably achievable (ALARA). The RPO tracks personnel exposures,
which are usually less than 0.5 mSv (50 mrem) per year. The PSU ALARA
program requires the RPO to investigate any annual personnel exposures
greater than 10 percent of the limit of 50 mSv (5000 mrem) specified in
10 CFR 20.1201. Personnel dosimeters mounted in the control room and
reactor bay provide a quarterly measurement of total radiation
exposures at those locations. These dosimeters typically measure annual
doses of less than 0.5 mSv (50 mrem) in the control room and less than
2 mSv (200 mrem) in the reactor bay. No changes in reactor operation
that would lead to an increase in occupational dose are expected as a
result of the proposed action.
The licensee conducts an environmental monitoring program to record
and track the radiological impact of PSBR operation on the surrounding
unrestricted area. The program consists of quarterly exposure
measurements at four locations on the site boundary and at two control
locations away from any direct influence from the reactor. The RPO
administers the program and maintains the appropriate records. Over the
past five years, the survey program indicated that radiation exposures
at the monitoring locations were not significantly higher than those
measured at the control locations. 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 the NRC staff's review of the past
five years of data, the NRC staff concludes that operation of the PSBR
does not have any significant radiological impact on the surrounding
environment. No changes in reactor operation that would affect off-site
radiation levels are expected as a result of license renewal.
Environmental Effects of Accidents
Accident scenarios are discussed in Chapter 13 of the PSBR SAR. The
maximum hypothetical accident (MHA) is the uncontrolled release of the
gaseous fission products contained in the gap between the fuel and the
fuel cladding in one fuel element to the reactor building and into the
environment. The licensee conservatively calculated doses to facility
personnel and the maximum potential dose to a member of the public. NRC
staff performed independent calculations to verify that the doses
represent conservative estimates for the MHA. Occupational doses
resulting from this accident would be well below 10 CFR Part 20 limit
of 50 mSv (5000 mrem). Maximum doses for members of the public
resulting from this accident would be well below 10 CFR Part 20 limit
of 1 mSv (100 mrem). The proposed action will not increase the
probability or consequences of accidents.
II. Non-Radiological Impacts
The PSBR core is cooled by a light water primary system consisting
of the reactor pool, a heat removal system, and a processing system.
Cooling occurs by natural convection, with the heated coolant rising
out of the core and into the bulk pool water. The large heat sink
provided by the volume of primary coolant allows several hours of full-
power operation without any secondary cooling. The heat removal system
transfers heat to the secondary system via a 1-MW heat exchanger. The
secondary system uses water pumped from the nearby Thompson Pond.
During operation, the secondary system is maintained at a higher
pressure than the primary system to minimize the likelihood of primary
system contamination entering the secondary system, and ultimately the
environment. The licensee conducts periodic leak tests of the heat
exchanger to further reduce the likelihood of secondary system
contamination.
Release of thermal effluents from the PSBR will not have a
significant effect on the environment. A storm sewer returns the heated
secondary coolant to Thompson Pond. According to the licensee, the
University maintains and complies with the appropriate Pennsylvania
Department of Environmental Protection permit for secondary water
discharge, and no violations of the permit have occurred. Given that
the proposed action does not involve any change in the operation of the
reactor and the heat load dissipated to the environment, the NRC staff
concludes that the proposed action will not have a significant impact
on the local water supply.
National Environmental Policy Act (NEPA) Considerations
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
The site occupied by the PSBR does not contain any Federally- or
State-protected fauna or flora, nor do the PSBR effluents impact the
critical habitats of any such fauna or flora.
II. Coastal Zone Management Act
The site occupied by the PSBR is not located within any managed
coastal zones, nor do the PSBR effluents 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 one historical site located on the PSU campus, the
Ag Hill Complex. The location of the Ag Hill Complex is approximately 1
km (0.6 Miles) East of the PSBR. Given the distance between the
facility and the Ag Hill Complex, continued operation of the PSBR will
not impact any historical sites. In 1991, the PSBR received the
American Nuclear Society Nuclear (ANS) Historic Landmark Award,
commemorated by a plaque located at the site. Continued operation of
the PSBR will not affect this historic designation. During a telephone
conversation between the NRC staff and the licensee on October 2, 2009,
the licensee stated that PSU has no plans to apply to have the PSBR
listed in the NRHP. Additionally, the licensee stated that any
modifications to the facility exterior must go through Campus Planning
and Design in the PSU Office of Physical Plant. This provides assurance
that any modifications would be made only after an appropriate review
by the University. Based on this information, the NRC finds that the
potential impacts of license renewal would have no adverse effect on
historic and archaeological resources at PSBR.
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.
[[Page 58322]]
IV. 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 PSBR. Such effects
may include ecological, cultural, human health, economic, or social
impacts. Minority and low-income populations are subsets of the general
public residing around the PSBR, and all are exposed to the same health
and environmental effects generated from activities at the PSBR.
Minority Populations in the Vicinity of the PSBR--According to 2000
census data, 4.3 percent of the population (approximately 634,000
individuals) residing within a 50-mile radius of PSBR identified
themselves as minority individuals. The largest minority group was
Black or African American (12,000 persons or 1.9 percent), followed by
Asian (7,700 or 1.2 percent). According to the U.S. Census Bureau,
about 9.4 percent of Centre County population identified themselves as
minorities, with persons of Asian origin comprising the largest
minority group (4.4 percent). According to census data 3-year average
estimates for 2005-2007, the minority population of Centre County, as a
percent of total population, had increased to 11.4 percent.
Low-Income Populations in the Vicinity of the PSBR--According to
2000 census data, approximately 13,000 families and 78,000 individuals
(approximately 7.9 and 12.4 percent, respectively) residing within a
50-mile radius of the PSBR 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 2005-2007 American Community Survey
3-Year Estimates, the median household income for Pennsylvania was
$47,913, while 11.9 percent of the state population was determined to
be living below the Federal poverty threshold. Centre County had a
lower median household income average ($42,976) and higher percentages
(18.5 percent) of individuals living below the poverty level,
respectively.
Impact Analysis--Potential impacts to minority and low-income
populations would mostly consist of radiological effects, however
radiation doses from continued operations associated with the license
renewal are expected to continue at current levels, and would be well
below regulatory limits.
Based on this information and the analysis of human health and
environmental impacts presented in this environmental assessment, the
NRC staff concludes that the proposed action would not have
disproportionately high and adverse human health and environmental
effects on minority and low-income populations residing in the vicinity
of the PSBR.
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 PSBR will eventually require decommissioning, at which
time the environmental effects of decommissioning will occur.
Decommissioning will be conducted in accordance with an NRC-approved
decommissioning plan which will require a separate environmental review
under 10 CFR 51.21. Cessation of facility operations would reduce
radioactive effluents. However, as previously discussed in this
environmental assessment, radioactive effluents resulting from facility
operations constitute only a small fraction of the applicable
regulatory limits. Therefore, the environmental impacts of license
renewal and denial of the application for license renewal are similar.
In addition, denial of the application for license renewal would cause
the benefits of teaching, research, and services provided by facility
operation to be lost.
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. 23 to Facility
Operating License No. R-2 for the Penn State Breazeale Reactor dated
January 27, 1986, which renewed the Facility Operating License for a
period of 20 years.
Agencies and Persons Consulted
In accordance with the agency's stated policy, on September 28,
2009, the 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 State official did comment on the
designation of the PSBR as an ANS Nuclear Historic Landmark. The
comment was informational in nature and the NRC staff responded by
including this information in this environmental assessment and noting
that continued operation of the facility will not adversely impact the
ANS Nuclear Historic Landmark designation.
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 December 6, 2005 (ML091250487), as supplemented
by letters dated October 31, 2008 (ML092650603); and April 2
(ML093030395), June 11 (ML092030312), September 1 (ML092580215), and
October 21, 2009 (ML092990409). 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].
Dated at Rockville, Maryland, this 4th day of November 2009.
For the Nuclear Regulatory Commission.
Linh Tran,
Senior Project Manager, Research and Test Reactors Branch A, Division
of Policy and Rulemaking, Office of Nuclear Reactor Regulation.
[FR Doc. E9-27282 Filed 11-10-09; 8:45 am]
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