Finding of No Significant Impact and Notice of Opportunity for a Hearing Renewal of Special Nuclear Material License SNM-1107; Westinghouse Electric Corporation Commercial Nuclear Fuel Division Columbia Fuel Fabrication Facility Columbia, SC

NUCLEAR REGULATORY COMMISSION

[Docket 70-1151]

Finding of No Significant Impact and Notice of Opportunity for a

Hearing Renewal of Special Nuclear Material License SNM-1107;

Westinghouse Electric Corporation Commercial Nuclear Fuel Division

Columbia Fuel Fabrication Facility Columbia, SC

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

of Special Nuclear Material License SNM-1107 for the continued

operation of the Westinghouse Electric Corporation, Commercial Nuclear

Fuel Division, Columbia Fuel Fabrication Facility (CFFF) located in

Columbia, South Carolina.

Summary of the Environmental Assessment

Identification of the Proposed Action

The proposed action is the renewal of the license to continue

manufacturing low-enriched nuclear fuel for a period of 10 years. The

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

special nuclear material in accordance with 10 CFR Part 70. CFFF is not

requesting any changes to the authorized activities at the site.

Principal activities at CFFF include the chemical conversion of uranium

hexafluoride (UF6) to uranium dioxide (UO2) powder by the

Ammonium Diuranate (ADU) Process or Integrated Dry Route (IDR);

fabricating the UO2 powder into pellets; loading the pellets into

fuel rods and final fuel assembly; and scrap recovery operations.

The Need for the Proposed Action

CFFF is one of several facilities in the United States which

fabricate fuel assemblies for light-water cooled nuclear reactors

(LWR). As long as the current demand for nuclear energy continues, the

production of the fuel must keep pace. Because the applicant is a major

supplier of fuel for LWRs, denial of the license renewal for this

facility would necessitate expansion of similar activities at another

existing fuel fabrication facility or the construction and operation of

a new plant.

Environmental Impacts of the Proposed Action

Effluent Monitoring

Gaseous, liquid, and solid effluents are produced from

manufacturing operations at CFFF. The effluents may contain small

quantities of \234\U, \235\U, \238\U, ammonia (NH3), calcium

fluoride (CaF2), and hydrofluoric (HF) gas. An

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effluent monitoring program is in place at the facility to ensure

releases to the environment are within Federal and State regulations

and are also as low as is reasonably achievable (ALARA).

Gaseous exhausts from the controlled area are routed through High

Efficiency Particulate Air (HEPA) filtration to remove entrained

uranium particulates prior to discharge to the environment. Exhausts

containing chemicals or uranium in soluble form are passed through

aqueous scrubbers, preceding the HEPA filters. Each release stack is

equipped with an isokinetic probe that continuously draws a sample

through a fiberglass filter paper. The filter paper is changed daily

and analyzed for uranium levels. Gaseous effluents are also sampled and

analyzed for ammonia and fluoride.

The State of South Carolina has issued an air quality permit

authorizing the use of the incinerator, boilers, and emergency diesel

generators. The current permit expired on January 31, 1995. However,

prior to expiration, Westinghouse submitted an application for renewing

this permit and they are negotiating with the State over the terms of

the new permit.

Liquid process wastes are treated in the Waste Treatment Facility

(WTF) and then pumped to the Congaree River via a 4-inch pipeline.

Waste treatment for the removal of uranium, ammonia, and fluorides

consists of filtration, flocculation, lime addition, distillation, and

precipitation in a series of holding lagoons. Compliance with Federal

and State release limits for radioactive material in the liquid

effluent is assured by passing the waste stream through on-line

monitoring systems or by manual sampling and analysis on a batch basis.

A review of the data indicates that radioactive liquid discharges have

been within Federal regulations.

Site sanitary sewage is treated in an extended aeration package

plant prior to discharge, either directly or through a polishing

lagoon. The discharge effluent is chlorinated, and mixed with treated

liquid process waste at the facility lift station.

Liquid process wastes and site sanitary sewage is combined and then

passed through a final aerator, followed by pH adjustment as required

and subsequently pumped to the Congaree River.

The WTF (advanced wastewater treatment) system provides additional

uranium removal from major liquid waste streams. Other small waste

streams are batch collected in quarantine tanks, sampled, and analyzed

prior to discharge to the WTF. Other miscellaneous contaminated liquid

wastes, from sources such as laboratory drains and controlled area

sinks, are discharged directly to a contaminated waste disposal system

where they are collected, filtered, sampled, analyzed, and released to

the WTF lift station. Wastes processed through the WTF are continuously

sampled at the point of discharge. The samples are composited and each

day's composite is then resampled and analyzed for gross alpha and

gross beta activity.

The State of South Carolina reissued a National Pollutant Discharge

Elimination System (NPDES) permit to Westinghouse authorizing discharge

from the sanitary and process wastewater streams to the Congaree River.

The previous permit expired on January 31, 1994. The current permit is

based on the Anti-Backsliding Rule on existing permit limits, Best

Professional Judgement (BPJ), and water quality considerations. Due to

the Anti-Backsliding Rule none of the parameter limits were increased.

However, based on BPJ and water quality considerations, the limits for

ammonia, fluoride, fecal coliforms were decreased. In addition, an

acute toxicity test requirement was added to the current permit.

A review of the NPDES permit data indicates that, for the most

part, the licensee has complied with the permit limitations with the

exception of the biological toxicity test. The licensee is working on

methods to ensure compliance with this test.

Low-level contaminated wastes are stored in a Waste Storage Area.

Prior to transfer to this area, contaminated items are visually

inspected to ensure that no accumulation of radioactive material is

present and are then surveyed and released in accordance with the

appropriate contamination limits.

Solid wastes are sorted as combustible and noncombustible and are

placed in specially designated collection containers located throughout

the work area. The wastes consist of paper, wood, plastics, metals,

floor sweepings, and similar materials which are contaminated by or

contain uranium. Following a determination that the wastes are sorted

properly, the contents are transferred to a waste processing station

located in the Contaminated Control Area.

Materials that are suited for thorough survey may be decontaminated

for free-release, or re-use, in accordance with the provisions of the

license. Most combustible wastes are packaged in compatible containers,

assayed for grams \235\U, and stored to await incineration.

Noncombustible wastes and certain combustible wastes are packaged in

compatible containers, compacted when appropriate, gamma scanned to

verify the uranium content, and placed in storage to await shipment for

recovery or disposal. Contaminated wastes are shipped to a licensed

burial facility.

Environmental Monitoring

The environmental media sampled for the environmental monitoring

program at CFFF includes air, vegetation, groundwater, surface water,

and soil. The program is designed to ensure compliance with State and

Federal regulations and to assess the impact to the environment from

site operations. Sample data for the period 1984 through 1994 were

reviewed to determine if plant operations were impacting the

environment.

Ambient air samples are collected at four locations onsite. The air

samplers run continuously with the sample being collected on a

particulate filter. This filter is changed weekly and, after the

appropriate decay period, analyzed for gross alpha activity. Ambient

air monitoring data indicate releases to the environment have been

within regulatory limits.

Soil is collected from the four ambient air monitoring locations

within the vicinity of the facility. The samples are analyzed for gross

alpha and beta.

A review of the sampling data demonstrates that there is no

indication of uranium accumulating in the soil at the sampling

locations.

The soil was also analyzed for fluoride. Annual average fluoride

values range from 0.1 ppm to 440 ppm. The annual average fluoride

levels since 1992 have been less than 1 ppm. There is no indication

that fluoride is accumulating in the soil.

Vegetation samples are collected from the four ambient air sampling

locations. Samples are analyzed for gross alpha and gross beta. A

review of the data indicates that there is no uptake of radioactive

material in the vegetation.

The vegetation is also analyzed for fluoride. Annual average

fluoride values range from 0.2 ppm to 3340 ppm. The annual average

fluoride levels since 1992 have been less than 1 ppm. There is no

indication of fluoride accumulating in the vegetation.

Surface water samples are collected from three locations onsite and

three locations on the Congaree River. These samples are collected

quarterly and analyzed for gross alpha and gross beta. A review of the

surface water data from 1984 through 1994 indicates that liquid

effluent discharges from the facility are not adversely impacting the

onsite surface water or the Congaree River.

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Groundwater is collected quarterly from 10 sampling wells onsite to

comply with NRC requirements. These samples are analyzed for gross

alpha, gross beta, and ammonia. Based on a review of the data from 1984

through 1994, there appears to be no radiological impact to the

groundwater from plant operations.

Groundwater samples are also analyzed for pH, ammonia, fluoride,

nitrate, and conductivity. Three of the wells near the lagoons have

elevated nitrate levels. However, samples from wells adjacent to Sunset

Lake and the swamp indicate nitrate levels less than detectable levels.

An EPA team visited the facility in early 1989 to perform a site

screening investigation which would evaluate past hazardous waste

handling practices and groundwater contamination. This screening

identified volatile organic contamination in the groundwater on the

plant site. In 1992, Westinghouse conducted an investigation to further

document the problem, and with input from South Carolina Department of

Health and Environmental Control (SCDHEC) developed a work plan to

study the contaminated area. The study indicated that the plume

consisted of perchlorethylene, trichlorethylene, and their degradation

products. A remedial design plan was developed and submitted to the

State of South Carolina for review and approval. Phase I of the plan

was implemented during the first quarter of 1995.

Fish samples are collected annually from the Congaree River

downstream of the plant discharge. The samples are analyzed for gross

alpha and gross beta activity and isotopic uranium. A review of the

data from 1984 through 1995 indicates that no uptake of radioactive

material by the fish is occurring.

Sediment is collected annually from the Congaree River near the

plant discharge to the river. Samples are analyzed for gross alpha,

gross beta, and fluoride. The data from 1984 through 1994 have been

reviewed and there is no indication of radioactive material

concentrating and accumulating at the sample location.

Radiological Impacts From the Proposed Action

The radiological impact from site operations was assessed by

calculating the dose to the nearest resident and to the local

population. Based on the information supplied by the licensee, the

nearest resident resides in the northwest sector, approximately 500

meters from the facility. The dose of the nearest resident was

calculated using EPA's COMPLY code, Screening Level 4, which is the

most conservative of the four levels, and guidance from NRC Regulatory

Guide 1.109, ``Calculation of Annual Doses to Man from Routine Releases

of Reactor Effluents for the Purpose of Evaluating Compliance with 10

CFR Part 50, Appendix I.'' Screening Level 4 uses site specific

meteorological information and assumes the resident produces his own

milk, meat and vegetables at home.

The Total Effective Dose Equivalent (TEDE) to the nearest resident

from licensed operations is 0.03 millirem/year. The natural background

radiation in the vicinity of Columbia, South Carolina is about 117

millirem/year. NRC regulations limit the dose to a member of the public

from licensed operations to 100 millirem/year. EPA limits the dose

received by a member of the public from licensed operations to 25

millirem/year.

Based upon 1990 census information, approximately 823,000 people

live within a 50-mile radius of the facility. The dose to the

population within the 50-mile radius of the facility would be 96,600

person-rem from the natural background of the area. The dose to the

population within the 50-mile radius from licensed operations at the

facility would be 0.29 person-rem.

Alternatives to the Proposed Action

Alternatives include the proposed action of renewing the license

application or denying the renewal request. The alternative of license

renewal would result in the continued operation of the facility for a

specific period of time. The environmental impact of the proposed

action will be discussed in this assessment.

The alternative of denying the renewal request would result in the

facility having to cease operations and begin decontamination and

decommissioning activities. The environmental impact of the alternative

of denying the license renewal would be the elimination of effluents

discharged to the air and water at the CFFF site. However, denial of

the license renewal would necessitate expansion of similar activities

at an existing facility or construction and operation of a new

facility. Because the environmental impacts would be transferred from

one location to another, there would be no net benefit to the

alternative of denying the license renewal. However, denying the

renewal request would be considered only if public health and safety

and environmental issues could not be resolved to the satisfaction of

the NRC.

Agencies and Persons Consulted

South Carolina Department of Health and Environmental Control,

Industrial & Agricultural Wastewater Division, Bureau of Water

Pollution Control. There are no objections to the license renewal of

the facility.

South Carolina Department of Health and Environmental Control,

Office of Environmental Quality Control, Bureau of Air Quality Control.

There are no objections to the license renewal of the facility.

Documents used to prepare the Environmental Assessment:

1. Westinghouse Electric Corporation, Application for Renewal of

Special Nuclear Material License No. SNM-1107, April 30, 1990.

2. Westinghouse Electric Corporation, Application for Renewal of

Special Nuclear Material License No. SNM-1107, April 30, 1995.

3. E.K. Reitler, Westinghouse Electric Corporation, letter to

Elaine Keegan, U.S. Nuclear Regulatory Commission, February 20, 1995.

4. Roger Fischer, Westinghouse Electric Corporation, letter to

Elaine Keegan, U.S. Nuclear Regulatory Commission, May 5, 1995.

5. U.S. Nuclear Regulatory Commission, ``Environmental Impact

Appraisal of the Westinghouse Nuclear Fuel Columbia Site (NFCS)

Commercial Nuclear Fuel Fabrication Plant,'' April 1977.

6. U.S. Nuclear Regulatory Commission, ``Environmental Assessment

for Renewal of Special Nuclear Material License No. SNM-1107,'' NUREG-

1118, May 1985.

7. U.S. Fish and Wildlife Services, Endangered and Threatened

Species of the Southeast United States (The Red Book), 1992.

Conclusion

The staff concludes that the impact to the environment and to human

health and safety from manufacturing nuclear fuel at this facility has

been minimal. The results from the environmental monitoring program

indicate no significant impact has occurred to the environment as a

result of site operations. Liquid and airborne effluents released to

the environment meet all Federal release criteria. The total effective

whole body dose received by the maximally exposed individual meets both

NRC and EPA regulations.

However, the staff has determined, to enhance effluent and

environmental monitoring programs, the following recommendations should

be incorporated as license conditions pending renewal of the license:

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1. The staff recommends that the licensee notify the NRC if the

conditions of the NPDES permit are revised or if the permit is revoked.

2. The staff recommends additional vegetation sampling be conducted

when the gross alpha activity exceeds 15 pCi/gram.

3. The staff also recommends the licensee develop and implement

action levels for the environmental samples.

Finding of No Significant Impact

The Commission has prepared an Environmental Assessment related to

the renewal of Special Nuclear Material License SNM-1107. 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 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

N.W., Washington, DC.

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 (Westinghouse

Electric Corporation, Commercial Nuclear Fuel Division, Drawer R,

Columbia, SC 29250), 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.

Dated at Rockville, Maryland, this 12th day of July 1995.

For the Nuclear Regulatory Commission.

Robert. C. Pierson,

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

NMSS.

[FR Doc. 95-17825 Filed 7-19-95; 8:45 am]

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