[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
