[Federal Register Volume 66, Number 203 (Friday, October 19, 2001)]
[Notices]
[Pages 53267-53269]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 01-26441]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-186]
University of Missouri--Columbia; University of Missouri--
Columbia Research Reactor; Environmental Assessment and Finding of No
Significant Impact
The U.S. Nuclear Regulatory Commission (NRC) is considering
issuance of an amendment to Amended Facility License No. R-103, issued
to the University of Missouri-Columbia (the licensee), for operation of
the University of Missouri-Columbia Research Reactor (MURR), located in
Columbia, Missouri.
Environmental Assessment
Identification of the Proposed Action
The proposed action would revise Amended Facility License No. R-103
to change the license expiration date from November 21, 2001, to
October 11, 2006, to recapture the construction time between the
issuance date of Construction Permit No. CPRR-68 (November 21, 1961)
and issuance of Facility Operating License No. R-103 (October 11, 1966)
to allow a 40-year operating license term.
The proposed action is in accordance with the licensee's
application for amendment dated December 27, 2000, as supplemented by
letters dated April 12 and June 6, 2001.
The Need for the Proposed Action
The proposed action is needed to recapture the time spent under the
construction permit to allow operation of the MURR reactor for a term
of 40 years from the date of issuance of the facility license.
Environmental Impacts of the Proposed Action
The MURR is located on a 7.5-acre lot in University Research Park,
about one mile (1.6 km) southwest of the University of Missouri main
campus in Columbia, Missouri. MURR is a pressurized, reflected, light-
water moderated and cooled heterogeneous design reactor. The reactor is
fueled with high-enriched, aluminum-clad, plate type fuel. The reactor
has a maximum steady-state power level of 10 Megawatts thermal [MW(t)]
with the reactor core located in a pressure vessel. The reactor
pressure vessel is located in a cylindrically shaped pool and is
covered by about 23 feet (7 m) of water during operation for radiation
shielding. The reactor pool is surrounded by a biological shield. The
reactor is located within a containment building.
The construction permit for the facility (CPRR-68) was issued to
the University of Missouri on November 21, 1961. On October 11, 1966,
Facility Operating License No. R-103 was issued to the University with
a maximum power level of 5 MW(t). On July 9, 1974, Amendment No. 2 to
the license was issued increasing the maximum operating power level to
10 MW(t). The facility normally operates on a 24-hour-a-day schedule
with a shutdown once a week for refueling and maintenance.
The NRC has completed its evaluation of the proposed action and
concludes that the proposed amendment to change the expiration date of
the facility license to recapture time between construction and
operation to allow for a 40-year operating license term will not result
in a significant increase in environmental impacts. The licensee has
not requested any changes to the facility design or operating
conditions as part of this amendment request. Data from the last ten
years of operation was assessed to determine the radiological impact of
the facility on the environment.
Environmental surveys are performed by measuring the exposure to 41
thermoluminescent dosimeters (TLDs) placed on and off site at various
distances and directions from the facility. The results of this
monitoring for all TLDs averaged by year from 1991 to 2000, and the TLD
with maximum exposure (both do not include TLDs affected by shipping
operations) is as follows:
------------------------------------------------------------------------
Average Maximum
Year (mrem/yr) (mrem/yr)
------------------------------------------------------------------------
2000.......................................... -1.3 18.6
1999.......................................... 13.5 43.5
1998.......................................... 3.4 51.9
1997.......................................... 9.2 34.8
1996.......................................... 9.2 34.9
1995.......................................... 14.6 44.2
1994.......................................... 20.5 49.7
1993.......................................... 18.1 28.2
1992.......................................... 6.3 26.7
1991.......................................... 4.4 27.3
------------------------------------------------------------------------
The 2000 average is slightly negative due to the inadvertent
exposure of a control TLD.
In addition, the licensee has calculated the dose to the individual
member of the public likely to receive the highest dose from air
emission of radioactive material to the environment to demonstrate
compliance with 10 CFR 20.1101(d). This regulation provides as low as
is reasonably achievable criteria for air emissions which must result
in an individual member of the public receiving a total effective dose
equivalent (TEDE) of less than 10 mrem per year. The results of
calculations for the years 1991-2000, is as follows:
------------------------------------------------------------------------
Dose (mrem/
Year yr)
------------------------------------------------------------------------
2000....................................................... 0.8
1999....................................................... 0.9
1998....................................................... 0.9
1997....................................................... 0.7
1996....................................................... 0.6
1995....................................................... 0.7
1994....................................................... 0.5
1993....................................................... 0.6
1992....................................................... 0.4
1991....................................................... 0.4
------------------------------------------------------------------------
[[Page 53268]]
These doses are within the constraint on air emissions of 10 mrem
per year total effective dose equivalent in 10 CFR 20.1101(d).
The radioactive material released from the facility in airborne
effluents is given as follows:
------------------------------------------------------------------------
Curies Curies
Year released released
(Argon-41) (Total)
------------------------------------------------------------------------
2000.......................................... 975 982
1999.......................................... 1130 1137
1998.......................................... 1130 1134
1997.......................................... 861 870
1996.......................................... 728 739
1995.......................................... 878 888
1994.......................................... 370 385
1993.......................................... 409 425
1992.......................................... 470 475
1991.......................................... 440 441
------------------------------------------------------------------------
Airborne effluent releases from the facility consist primarily of
argon-41. This is characteristic for research reactors. The releases
from the facility met the average concentration requirements of the
facility technical specifications. The increase in the amount of
radioactive effluents reported released between 1994 and 1995 was the
result of a change in the method used by the licensee to sample the
effluent. Prior to 1995, the results were based on the analysis of a
daily grab sample. From 1995, the activity released was based on
calculations performed on data recorded from the gas channel of the
exhaust stack radioactivity monitor which is in operation 24 hours a
day. Analysis of continuous data provided better accuracy than the grab
sample method that only measured the radioactive material concentration
in the airborne effluent once per day at the time the sample was taken.
Liquid effluent releases to the sanitary sewer were as follows:
------------------------------------------------------------------------
Curies
released Curies
Year (Hydrogen- Released
3) (Total)
------------------------------------------------------------------------
2000.......................................... 0.1199 0.1420
1999.......................................... 0.1670 0.1740
1998.......................................... 0.5901 0.5980
1997.......................................... 0.1460 0.1510
1996.......................................... 0.1487 0.1560
1995.......................................... 0.0818 0.0900
1994.......................................... 0.1089 0.1270
1993.......................................... 0.2574 0.3160
1992.......................................... 0.1711 0.2150
1991.......................................... 0.2094 0.2580
------------------------------------------------------------------------
Liquid effluent releases from the facility to the sanitary sewer
consisted primarily of hydrogen-3. The licensee releases liquid
effluent only to the sanitary sewer. The NRC inspection program
confirmed that monthly concentrations met regulatory requirements found
in Appendix B Table 3 of 10 CFR Part 20 in accordance with 10 CFR
20.2003.
Shipments of radioactive waste offsite for disposal at approved
sites were as follows:
------------------------------------------------------------------------
Volume
Year (cubic Activity
feet) (mCi)
------------------------------------------------------------------------
2000.......................................... 1207.5 249
1999.......................................... 565.0 281
1998.......................................... 910.0 53
1997.......................................... 420.0 404
1996.......................................... 337.5 1409
1995.......................................... 0.0 0
1994.......................................... 460.0 1228
1993.......................................... 392.0 60,105
1992.......................................... 679.0 1924
1991.......................................... 772.5 1146
------------------------------------------------------------------------
The NRC inspection program confirmed that waste shipments met the
requirements of the regulations in 10 CFR Part 20 for waste disposal.
The licensee did not ship radioactive waste offsite in 1995.
Shipments to return spent reactor fuel to the Department of Energy
(DOE) were as follows:
------------------------------------------------------------------------
Year Shipments
------------------------------------------------------------------------
2000....................................................... 1
1999....................................................... 2
1998....................................................... 6
1997....................................................... 4
1996....................................................... 2
1995....................................................... 4
1994....................................................... 1
1993....................................................... 3
1992....................................................... 9
1991....................................................... 0
------------------------------------------------------------------------
Eight fuel elements are in each shipment. The fuel is returned to
DOE facilities at the Savannah River Plant in Aiken, South Carolina.
The NRC inspection program confirmed that fuel shipments met NRC and
Department of Transportation requirements for the shipment of
radioactive material.
Radiological releases from the facility and associated doses to the
public are within regulatory limits or facility technical
specifications and do not have a significant impact on human health or
the environment. Monitoring of radiation levels in the environment
includes soil, vegetative, and water sampling and direct radiation
readings. Results of the monitoring program are reported in the Reactor
Operations Annual Report and indicate that the facility does not have a
significant impact on human health or the environment. Releases of
radioactive material from the facility to the environment for the
proposed construction permit recapture period are estimated to continue
at levels similar to those above, which are well within regulatory
limits.
Occupational doses to MURR staff and users meet the regulatory
requirements found in 10 CFR part 20, subpart C, and are as low as is
reasonably achievable. No changes in reactor operation that would lead
to an increase in occupational dose are expected as a result of the
proposed action.
The proposed action will not increase the probability or
consequences of accidents, no changes are being made in the types of
any effluents that may be released off site, and there is no
significant increase in occupational or public radiation exposure.
Therefore, there are no significant radiological environmental impacts
associated with the proposed action.
With regard to potential non-radiological impacts, the proposed
action does not have a potential to impact historic properties. The
facility uses and disposes of small quantities of chemicals [e.g., up
to about 5 gallons (20 liters) per year of hydrochloric acid, nitric
acid, aqua regia and isopropyl alcohol] in research laboratories. These
chemicals are disposed of in compliance with Environmental Protection
Agency (EPA) and Missouri Department of Natural Resources requirements
by the University of Missouri Environmental Health and Safety
Department. These chemical forms and quantities are consistent with
small laboratory use at universities.
The quality of the secondary cooling water is maintained using two
commercial biocides, a corrosion inhibitor, and sulfuric acid (for pH
control). These chemicals are similar to those used in cooling towers
for the air conditioning systems of large buildings and enter the
environment by evaporation from the tower to the air and by blowdown to
the sanitary sewer. About 105 gallons (400 liters) of the two biocides,
700 gallons (2650 liters) of corrosion inhibitor, and 4000 gallons
(15,150 liters) of sulfuric acid are used annually. The use of these
chemicals is approved by EPA. These chemicals are stored in a manner
that will contain the chemicals in the event of material storage
container failure. The use and disposal of these chemicals will not
have a significant impact on the environment. The proposed action will
not result in significant increases in the use of these chemicals.
The facility uses approximately 38 million gallons of water
annually. The water is supplied by university owned and maintained deep
wells which provide water to the campus. Most of
[[Page 53269]]
the water (28 million gallons) is used in the cooling tower with the
majority of the water lost to the atmosphere as water vapor. Wastewater
from the facility discharges to the City of Columbia sewer system and
is treated at the Columbia Regional Wastewater Treatment Plant.
The Missouri Department of Conservation has determined that no
Federal or State listed plants or animals are known to occur on the
MURR site, but did identify two species in the vicinity of the project
site. One species, the Topeka Shiner, is listed as endangered. MURR
withdraws a minimal amount of groundwater for reactor operation, has no
major refurbishment or construction activities planned, and will have
no significant change in the types or amounts of effluents leaving the
facility as a result of construction permit recapture. Therefore, the
proposed action is not expected to affect aquatic and terrestrial
biota. The staff concludes there are no significant non-radiological
environmental impacts associated with the proposed action.
Accordingly, the NRC concludes that there are no significant
environmental impacts associated with the proposed action.
Alternatives to the Proposed Action
As an alternative to the proposed action, the staff considered
denial of the proposed action (i.e., the ``no-action'' alternative).
Denial of the proposed action would result in expiration of the current
license in November 2001, and the commencement of decommissioning if an
application for license renewal is not made. If the application is
denied, it is expected that the licensee would apply for renewal of the
license. With operation under the proposed action or with a renewed
license or during the evaluation of a timely renewal application, the
environmental impacts of the proposed action and the alternative are
similar.
If the Commission denied the application for license renewal,
facility operations would end and decommissioning would be required
with no significant impact on the environment. The environmental
impacts of the proposed action and this alternative action are similar.
In addition, the benefits of education and research conducted by the
facility would be lost.
Alternative Use of Resources
This action does not involve the use of any resources not
previously considered in the Hazards Analysis Report prepared for
initial licensing of the facility and the power upgrade to 10 MW(t).
Agencies and Persons Consulted
In accordance with its stated policy, on September 14, 2001, the
staff consulted with the Missouri State official, Mr. Ron Kucera,
Director of Intergovernmental Cooperation and Special Projects of the
Missouri Department of Natural Resources, regarding the environmental
impact of the proposed action. The State official had no comments. In
addition, the NRC determined to exercise its discretion to circulate an
Environmental Assessment and Finding of No Significant Impact to the
public for a 30-day comment period in response to a request from the
State of Missouri Department of Natural Resources. The Notice of
``Request for Public Comment, Environmental Assessment and Finding of
No Significant Impact'' appeared in the Federal Register on August 1,
2001 (66 FR 39803). During the comment period, the staff received 12
comment letters. All of the comments have been reviewed by the NRC. The
majority of the comments received related to the operation of the
reactor and other issues not related to the EA or the license amendment
request. In response to comments relevant to the EA, several changes
were made to the text of the EA to clarify issues raised in the
comments.
A ``Discussion of Comments Received on the Environmental Assessment
for the University of Missouri-Columbia Construction Permit Recapture
Amendment'' has been prepared by the NRC staff. This document contains
the NRC staff's discussion and response to the public comments relative
to the EA and copies of the comment letters. This document has
accession number ML012850463. Members of the public may view the
document by using ADAMS or contacting the Public Document Room staff as
discussed below.
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 27, 2000, as supplemented by letter
dated April 12 and June 6, 2001, and the NRC staff's ``Discussion of
Comments Received on the Environmental Assessment for the University of
Missouri-Columbia Construction Permit Recapture Amendment,'' which are
available for public inspection, and can be copied for a fee, at the
U.S. Nuclear Regulatory Commission's Public Document Room (PDR),
located at One White Flint North, 11555 Rockville Pike (first floor),
Rockville, Maryland. The NRC maintains an Agencywide Documents Access
and Management System (ADAMS), which provides text and image files of
NRC's public documents. These documents may be accessed through the
NRC's Public Electronic Reading Room on the internet at
http://www.nrc.gov/NRC/ADAMS/index.html. Persons who do not have access
to ADAMS or who have problems in accessing the documents located in
ADAMS may contact the PDR reference staff at 1-800-397-4209, 301-415-
4737 or by email at [email protected].
Dated at Rockville, Maryland, this 12th day of October 2001.
For the Nuclear Regulatory Commission.
Eugene V. Imbro,
Acting Chief, Operational Experience and Non-Power Reactors Branch,
Division of Regulatory Improvement Programs, Office of Nuclear Reactor
Regulation.
[FR Doc. 01-26441 Filed 10-18-01; 8:45 am]
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