[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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