[Federal Register Volume 60, Number 139 (Thursday, July 20, 1995)]
[Notices]
[Pages 37481-37484]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-17825]



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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 

[[Page 37482]]
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. 

[[Page 37483]]

    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: 

[[Page 37484]]

    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]
BILLING CODE 7590-01-P