Environmental Statements; Availability, etc.: Combustion Engineering, Inc.

NUCLEAR REGULATORY COMMISSION

[Docket 70-36]

Environmental Statements; Availability, etc.: Combustion

Engineering, Inc.

The U.S. Nuclear Regulatory Commission is considering the renewal

of Special Nuclear Material License SNM-33 for the continued operation

of the Combustion Engineering, Inc. (CE), Hematite Nuclear Fuel

Manufacturing Facility, for 10 years.

Summary of the Environmental Assessment

Identification of the Proposed Action

The proposed action is the renewal of License SNM-33, allowing CE

to continue manufacturing low-enriched nuclear fuel for 10 years. The

current license authorizes CE to receive, possess, use, and transfer

special nuclear material in accordance with 10 CFR part 70 and source

material in accordance with 10 CFR part 40. This license also allows CE

to delivery radioactive material to a carrier for transportation in

accordance with 10 CFR part 71. CE produces low-enriched (5

percent U-235) ceramic nuclear fuel for light-water cooled reactors.

The Need for the Proposed Action

The proposed action is needed for CE to continue to produce low-

enriched nuclear fuel pellets which will ultimately be used by

commercial nuclear power plants to produce electricity. Since CE is one

of only a few facilities that manufacture nuclear fuel in this country,

there remains a need for the fuel by the nuclear power industry.

Environmental Impacts of the Proposed Action

Airborne effluents from process areas and process equipment

involving uranium in a dispersible form are subject to air filtering,

prior to release to the atmosphere. Effluents from the process areas

are continuously collected on a particulate filter and are analyzed for

gross alpha activity. The monitoring data for 1982 through September

1993 demonstrates that the levels of gross alpha activity released from

the site do not exceed the limits specified in 10 CFR part 20, Appendix

B, Table II, Column 1.

There are no planned releases of radioactive liquid wastes from

routine production processes. Liquids with low-uranium content, such as

mop water, cleanup water, and grinder coolant water, are collected and

then evaporated to recover the uranium. Liquids with higher uranium

content are processed to recover the uranium, usually by precipitation

and filtration. Process filtrates, including wet recovery system

filtrate and spent scrubber solutions, are routed to a calibrated tank,

mixed, sampled, and the filtrates are then evaporated, solidified with

concrete, and packaged for shipment to a licensed burial site.

A potential source of radioactive liquid waste is from the laundry,

sink and shower areas, and the chemistry laboratory. The laundry water

is filtered and sampled prior to discharge to the sanitary sewer

system. The water from change room sinks and showers is also discharged

through the sanitary waste system. Effluents from the sanitary waste

system enter the site creek immediately below the site pond dam. A grab

sample of the water is taken each week and analyzed for gross alpha and

beta activities. The chemistry laboratory discharges to the storm drain

system. While analytical residues are recycled to recover the uranium

and therefore do not contribute to the effluents, when the laboratory

glassware is cleaned, small amounts of liquids wash down the sinks and

are discharged to the storm drain system. The storm drain system

discharges into the site pond which overflows to form the site creek.

The overflow is sampled weekly and analyzed for gross alpha and beta.

Liquid effluent sample data for 1982 through September 1993 was

reviewed and indicates that the results are a small fraction of the

values set forth in 10 CFR part 20, Appendix B, Table II, Column 2.

CE conducts an environmental sampling program to determine if site

operations are impacting the environment. Air, soil, vegetation,

surface water, and ground water samples are collected from various

locations on or near the plant site. Review of the data for 1982

through September 1993 indicates there is no significant impact to the

environment from manufacturing operations.

A dose assessment was performed to evaluate the impact from site

operations to the maximally exposed individual who would be the nearest

resident. The maximally exposed individual is located 950 feet (290 m),

west-northwest of the plant site. The effective whole body dose for the

maximally exposed individual is 3.31E-02 mrem/year. The critical organ

for this exposure would be the lungs, with a dose of 1.90E-01 mrem/

year. The annual dose received by the nearest resident is below the

federal dose limits set forth in 10 CFR part 20 and 40 CFR part 190,

500 mrem/year and 25 mrem/year, respectively.

Conclusion

Liquid and airborne effluents released to the environment are well

below all regulatory limits. Results of the environmental monitoring

program have shown that environmental radiation levels are not

increasing as a result of site operations. The total whole body dose

received by the maximally exposed individual from site operations is

well below federal limits. Therefore, the staff concludes that the

impact to the environment and to human health and safety from

manufacturing nuclear fuel at this site has been minimal.

Alternatives to the Proposed Action

The alternative to the proposed action would be to deny the license

renewal. Not renewing the operating license would cause CE to cease

operations and begin decontamination and decommissioning activities at

the site. While terminating licensed activities at CE may create a

minimal positive effect on the immediate environment, the socioeconomic

impact of denying the license would adversely affect the area because

CE is one of the largest employers in the area. This alternative would

be considered if there were public health and safety issues that could

not be resolved to the satisfaction of the NRC.

Agencies and Persons Consulted

Staff utilized the application dated November 22, 1989, and

additional information dated October 11, and December 16, 1991, and

December 10, 1993. Staff toured the CE facility on August 18 and 19,

1990. The region III inspector and CE staff were consulted in preparing

this document. The staff also contacted personnel from the State of

Missouri, Department of Natural Resources, Air Pollution Control

Program.

Finding of No Significant Impact

The Commission has prepared an Environmental Assessment related to

the renewal of Special Nuclear Material License SNM-33. On the basis of

the assessment, the Commission has concluded that environmental impacts

that would be created by the proposed licensing action would not be

significant and do not warrant the preparation of an Environmental

Impact Statement. Accordingly, it has been determined that a Finding of

No Significant Impact is appropriate.

The Environmental Assessment and the above documents related to

this proposed action are available for public inspection and copying at

the Commission's Public Document Room at the Gelman Building, 2120 L

Street NW., Washington, DC, and the Local Public Document Room located

at the Jefferson College Library, 1000 Viking Drive, Hillsboro, MO.

Opportunity for a Hearing

Any person whose interest may be affected by the issuance of this

renewal may file a request for a hearing. Any request for hearing must

be filed with the Office of the Secretary, U.S. Nuclear Regulatory

Commission, Washington, DC 20555, within 30 days of the publication of

this notice in the Federal Register; be served on the NRC staff

(Executive Director for Operations, One White Flint North, 11555

Rockville Pike, Rockville, MD 20852), and on the licensee (Combustion

Engineering, Inc., P.O. Box 107, Hematite, Missouri, 63047); and must

comply with the requirements for requesting a hearing set forth in the

Commission's regulation, 10 CFR part 2, Subpart L, ``Informal Hearing

Procedures for Adjudications in Materials Licensing Proceedings.''

These requirements, which the requestor must address in detail,

are:

1. The interest of the requestor in the proceeding;

2. How that interest may be affected by the results of the proceeding,

including the reasons why the requestor should be permitted a hearing;

3. The requestor's areas of concern about the licensing activity that

is the subject matter of the proceeding; and

4. The circumstances establishing that the request for hearing is

timely, that is, filed within 30 days of the date of this notice.

In addressing how the requestor's interest may be affected by the

proceeding, the request should describe the nature of the requestor's

right under the Atomic Energy Act of 1954, as amended, to be made a

party to the proceeding; the nature and extent of the requestor's

property, financial, or other (i.e., health, safety) interest in the

proceeding; and the possible effect of any order that may be entered in

the proceeding upon the requestor's interest.

For the Nuclear Regulatory Commission.

Dated at Rockville, Maryland, this 17th day of March 1994.

Robert C. Pierson,

Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards,

NMSS.

[FR Doc. 94-7209 Filed 3-25-94; 8:45 am]

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