[Federal Register Volume 62, Number 91 (Monday, May 12, 1997)]
[Notices]
[Pages 25975-25978]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 97-12365]
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NUCLEAR REGULATORY COMMISSION
[Docket 70-1113]
Finding of No Significant Impact and Notice of Opportunity for a
Hearing; Renewal of Special Nuclear Materials License SNM-1097, General
Electric Company, Wilmington, NC
The U.S. Nuclear Regulatory Commission (the NRC) is considering the
Renewal of Special Nuclear Materials License SNM-1097 for the continued
operation of General Electric (GE) Company's Nuclear Energy Production
Facility located in Wilmington, North Carolina. The facility
manufactures low-enriched uranium fuel for commercial nuclear power
reactors. The NRC has determined not to prepare an environmental impact
statement for the proposed action, because the renewal of License SNM-
1097 will not have a significant effect on the quality of the human
environment for reasons described in the environmental assessment (EA).
Summary of the Environmental Assessment
Identification of the Proposed Action
The proposed action is the renewal of GE's Special Nuclear
Materials License SNM-1097 for ten years. With this Renewal, GE will
continue to operate the Wilmington, North Carolina, facility to convert
low-enriched uranium hexafluoride to uranium dioxide pellets and to
fabricate fuel assemblies for light
[[Page 25976]]
water reactors. GE is authorized to possess and use up to 50,000 kg of
uranium-235 (235U) contained in uranium compounds enriched
up to 5 weight percent in 235U.
The facility converts low-enriched uranium hexafluoride
(UF6) to uranium dioxide (UO2) powder, presses
the UO2 into pellets, loads the pellets into fuel rods, and
assembles the fuel rods into fuel assemblies. The UF6 to
UO2 conversion is currently done using an ammonium diuranate
(ADU) process. However, with license renewal GE intends to begin using
a new dry conversion process (DCP), which will eventually replace the
ADU process. The EA considers both the impacts of continued operation
of the ADU process and the impacts from the DCP, which are expected to
be significantly reduced.
Need for the Proposed Action
GE performs a necessary service for the commercial nuclear power
industry by fabricating fuel for light water reactors. Currently, GE is
one of four producers in the United States of low-enriched uranium fuel
for commercial reactors. Denial of the license renewal application is
an alternative available to the NRC, but would require expansion of
fuel production capacity at an existing facility or transfer of fuel
fabrication activities to a new facility.
Environmental Impacts of the Proposed Action
The continued operation of the GE facility will result in the
continued release of low levels of radioactive and nonradioactive
materials to the environment. These include uranium, fluoride, ammonia,
and nitrates. Under accident conditions, the facility could release
higher concentrations over a short period of time. GE uses a number of
controls to reduce the release of effluents. These effluent streams as
well as the environment surrounding the facility are closely monitored.
The effluent controls, monitoring program, and environmental impacts
from routine and non-routine operations are discussed in detail in the
EA prepared by the NRC for this licensing action.
Effluent Controls and Monitoring
The GE facility produces gaseous, liquid, and solid effluent
streams. Gaseous effluents are controlled by use of high efficiency
particulate air (HEPA) filtration and appropriate permitted scrubbers
when necessary. Where grinding, mixing, milling, or handling of
UO2 powder exists, vented hoods and glove boxes are used.
Liquid effluents are controlled by the use of treatment systems and
wastewater retention basins designed to reduce the concentration of
contaminants prior to discharge to the Northeast Cape Fear River, via
an on-site effluent channel. Solid wastes are managed through a
combination of segregation, reprocessing, off-site disposal, recycling
and incineration.
Effluents are monitored at or just prior to the point of release.
Gaseous stack effluents are sampled continuously under isokinetic flow
conditions. Samples are analyzed on a daily or weekly basis for gross
alpha activity. Several stacks are also sampled to monitor fluoride
releases. Liquid effluents from operations are sampled at the outfall
of the final process basins using flow proportional composite samplers.
Samples are analyzed daily for uranium, weekly for gross alpha and
gross beta particle activity, and semi-annually for technetium-99. Non-
radiological parameters such as nitrogen, fluoride, and metals are
monitored in compliance with National Pollutant Discharge Elimination
System (NPDES) permits. Sanitary wastes are sampled at the sanitary
outfall to the site effluent channel, also in compliance with NPDES
permits. Actual sampling parameters and frequency may vary with NPDES
permit or operational changes. Solid wastes are surveyed prior to
treatment or off-site disposal.
Action limits, specified in the GE facility operating procedures,
are set to ensure investigation of unusual concentrations and
corrective actions as necessary. This monitoring program is revised as
appropriate to accommodate changes in operations, the emergence of
newly-acquired information, or regulatory agency permits and other
authorizations. The effluent monitoring program will be expanded with
the new DCP. This will include monitoring of new process off-gas and
building ventilation systems.
Environmental Monitoring
GE conducts an environmental monitoring program that samples air,
vegetation, surface water, sediment, and groundwater for radioactive
and nonradioactive contaminants. This information is used to determine
impacts to the surrounding area due to facility operations.
Continuous ambient air monitoring for gross alpha activity is
conducted at six air sampling stations located in the predominant wind
directions from fuel manufacturing operations, along the nearest site
boundary, and in the direction of the nearest offsite residences. At
the southwest and northeast ambient air sampling points, semi-annual
sampling for fluoride content in forage grass is also conducted.
Surface water is monitored by sampling the Northeast Cape Fear
River both upstream and downstream of the effluent channel discharge
point near the GE-Wilmington dock. Monthly upstream grab samples and
weekly downstream composite samples are analyzed for uranium content.
In addition, non-radiological analyses are performed weekly to
quarterly including pH, ammonia, nitrate, nitrite, temperature,
zirconium, conductivity, BOD5, and fecal coliform per NPDES permit.
Sediment samples from the effluent channel are collected at three
locations: at the final process basin outfall, above the effluent
channel dam, and below the effluent channel dam. These samples are
collected semiannually and analyzed for uranium concentration. Samples
are also taken of the sediment in the storm water channel draining the
controlled access fuel manufacturing area. In addition, soil samples
are collected from several on-site and off-site locations and analyzed
for uranium content.
To monitor the impact of the facility on groundwater, numerous
wells have been installed. Shallow monitoring wells were installed in
the uppermost aquifer in the immediate proximity of potential sources
of contamination such as lagoons or selected waste storage areas. In
addition, monitoring wells for the deeper aquifer, which is the
principal water supply in the area, have been installed to provide
information on the quality of this water supply. In each of these
monitoring systems, particular attention is given to the presence of
nitrate, which is common to the bulk of the treated effluent streams
and is not as readily attenuated in the subsurface as are some of the
other potential contaminants.
Impacts From Normal Operations
No measurable impacts have been observed to air, surface water, or
vegetation due to releases from the GE facility. However, there have
been impacts to the shallow and the principal aquifers at the site. In
addition, historic discharges have contaminated soil beneath the
process building and adjacent to waste water impoundments and disposal
trenches for calcium fluoride.
Between 1989 and 1995, levels of gross alpha activity above
background were identified on several occasions in a series of wells
installed in the shallow aquifer near the final process basins. Uranium
was detected in one of the wells. Measurements of nitrate,
[[Page 25977]]
ammonia, and fluoride in these wells were at background levels. GE is
currently assessing these data to determine the significance and fate
of the contamination.
In addition to the wells near the final process basins, one well
near the waste treatment facility, showed uranium and gross alpha
activity above background levels. This well, completed in the shallow
aquifer, also showed elevated levels of nitrate, ammonia, and fluoride
from 1989 to 1995. It is believed that the groundwater near the well
was contaminated in 1986 from ammonium fluoride waste water as a result
of a leak in an overhead pipe. Corrective actions were taken and the
fluoride and ammonia levels have generally decreased in the well since
1987. Although average nitrate levels decreased from 1987 to 1991,
levels have begun to increase since that time. GE staff representatives
indicate that assessment of these data continues.
Elevated concentrations of nitrate, fluoride, and uranium were also
measured in the shallow aquifer beneath the manufacturing buildings.
The contamination was due to the seepage of liquids through a seam in a
concrete floor in the 1970's and 1980's. When the contamination was
discovered, the floor seams were repaired and the contaminated soil was
removed. In addition, a shallow horizontal groundwater collection
system was installed to contain and collect localized contaminated
groundwater.
Although there has been an impact to the shallow aquifer, GE has
put into place measures to assess and to mitigate these impacts. There
is no indication that radiological contamination has migrated offsite,
and therefore, impacts to the offsite population are not expected.
Remediation of this contamination may be necessary at the time of
decommissioning prior to termination of the license and release of the
facility.
The routine monitoring program also identified traces of organics
(chlorinated solvents and 1,1,1-trichloroethylene) in the principal
aquifer in 1991. The contamination was the result of activities at the
site which were discontinued over a decade ago. When the contaminants
were discovered, additional monitoring wells were added to both the
site boundaries and the site interior for the shallow and the principal
aquifer. In addition, pump and treat methods were initiated to contain
the spread of contamination. The North Carolina Department of
Environmental Quality regulates these monitoring and corrective action
programs and maintains all documents concerning this issue.
The release of radioactive material to air and water from the GE
facility represents a potential negative impact on the health and
safety of the surrounding population. The primary component of this
impact is an incremental increase in the risk of cancer due to low
levels of radiation exposure. The impacts due to long-term releases
from normal operations are summarized below.
The impact is calculated and presented in terms of committed
effective dose equivalent (CEDE) and organ doses resulting from a
single year of operations. For doses resulting from the inhalation or
ingestion of uranium, this quantity is the total effective dose
equivalent (TEDE) (or organ dose) that will accrue to an individual
over a 50-year period beginning with the year the intake occurs. Doses
to a hypothetical maximally exposed individual (MEI) are summarized in
this section. A detailed description of the calculational methods used
for the dose assessment is provided in the EA.
The radionuclide doses were estimated using the Hanford
Environmental Radiation Dosimetry Software System GENII computer code.
Atmospheric release exposure pathways included inhalation, ingestion of
contaminated crops and resuspended dirt, and external exposure to the
airborne plume and contaminated ground. Liquid release exposure
pathways included ingestion of contaminated drinking water, fish,
mollusks, and crustaceans.
Based on air effluent data for the past five years, the GE facility
releases approximately 100 microcuries of gross alpha particle activity
per year. This activity is expected to decrease by 50 percent when the
DCP replaces the ADU conversion process. However, doses were
conservatively calculated assuming a release of 300 microcuries of
gross alpha particle activity per year. The TEDE to the MEI at the site
boundary was estimated to be 0.001 mSv/yr (0.1 mrem/yr), the dose to
the nearest resident, located 760 m south of the facility was estimated
to be about 4E-4 mSv/yr (0.04 mrem/yr), and the dose to the population
was estimated to be 0.0009 person-Sv/yr (0.09 person-rem/yr).
Inhalation is the major exposure pathway contributing 99.9 percent of
the dose.
Liquid effluents from the facility are released to the Northeast
Cape Fear River. Measured uranium concentrations at the site dock, near
the effluent outfall averaged 2.8E-9 microcuries per milliliter for
1989-1994. This river is not used as a drinking water supply for area
residents. However, the maximally exposed individual was assumed to use
river water and river food products at the GE Wilmington dock. The
radionuclide concentration released in liquid effluent is expected to
decrease when the DCP replaces the ADU process. The TEDE to the MEI was
estimated to be 0.007 mSv/yr (0.7 mrem/yr) for the current ADU process,
0.001 mSv/yr (0.1 mrem/yr) for the DCP process, and 0.008 mSv/yr (0.8
mrem/yr) during the transitional period.
NRC regulations (10 CFR 20.1301) require that the Total Effective
Dose Equivalent (TEDE) for members of the public not exceed 1.0 mSv
(100 mrem) per year. The TEDE is the sum of the effective dose
equivalent from exposure to external radiation for one year and the
CEDE defined above. Estimated doses for all releases from GE are small
fractions of the applicable limits.
Radiological impacts to workers at the GE facility were also
considered as part of the EA. During 1994 and 1995, approximately 1000
radiation workers at the GE plant were potentially exposed to
radioactive materials. The TEDE to the average worker during this time
was 0.39 cSv (0.39 rem). The maximum TEDE that any worker received
during these years was 2.1 cSv (2.1 rem) during 1994 and 2.4 cSv (2.4
rem) in 1995. These doses are well below the NRC limit of 5 cSv per
year (5 rem/yr) in 10 CFR 20.1201. After the ADU to DCP transition
period is over, it is anticipated that occupational exposures would
decrease because of a less complex process, new equipment, and a better
separation between the worker and the nuclear material.
Monitoring data have shown no significant impact from radiological
or non-radiological releases on surface water, sediment, soil,
groundwater, air quality, or biota outside the boundary of the GE
facility. GE has an excellent NPDES compliance record. Although some
impact on groundwater and soil has occurred, GE is addressing those
issues. GE operations are expected to have little or no impact on
cultural resources, and to have a positive socioeconomic impact.
Although there are some minority communities located within three
miles of the facility, no high and adverse impacts are projected on
these communities. Doses to individuals would be much greater at the
property boundary of the site. These doses are well below NRC
regulatory limits. Consequently, there are no environmental justice
impacts associated with the renewal.
[[Page 25978]]
Impacts From Accidental Releases
Release of radioactive or hazardous materials under abnormal or
accident conditions poses a potential risk to public health and safety
and the environment. The potential consequences of these accidents
include personal injury, health effects from acute exposures to toxic
materials, non-stochastic effects from acute radiation exposure, and
risk of latent cancer fatality from exposure to radioactive material.
Most of these risks are to workers at the facility, rather than to
members of the public.
Severity Category I and Category II accidents resulting in the
release of radioactive materials were examined in the EA. Category I
represents accidents that could be anticipated to occur at least once
during the lifetime of the facility. Category II represents accidents
that would not be expected to occur during the lifetime of the
facility, but are considered credible accidents under highly unusual
and unlikely conditions. These include two accidents involving the
release of non-radioactive materials (hydrofluoric acid and hydrogen).
The accident analyses demonstrated that no adverse health effects
would be expected to the off-site population due to the Category I
accidents or to the non-radiological accidents. However, Category II
accidents including a large UF6 cylinder fire that occurs in
the outside storage area at the facility, a defluorinator/calciner
explosion that results in a building breach, a major criticality
accident, or a major facility fire that involves a large amount of
UO2 powder could result in significant doses or toxicity
effects to off-site individuals. However, the occurrence of these
accidents is extremely unlikely. In addition, the licensee has
developed operating and emergency procedures to control and minimize
the effects of these types of accidents. Therefore, license renewal
will not have a significant impact on the general population.
Conclusion
The staff concludes that the impact to the environment and to human
health and safety from operations at this facility has been and is
expected to remain minimal. Results of the environmental monitoring
program conducted during the previous licensing period indicate no
significant impact to the environment as a result of site operations.
Radioactive materials in effluents released to the environment are well
below regulatory limits. The total dose received by the maximally
exposed individual is well below federal regulatory limits.
Alternative to the Proposed Action
An alternative to the proposed action is to deny renewal of the
license. In this case, GE would shut down processing of special nuclear
material to produce nuclear fuel, and would decontaminate and
decommission (D&D) the site in accordance with an approved plan. With
this action, release of radiological and non-radiological effluents
from licensed operations would cease in the near term, as would the
minimal impacts resulting from those releases. Non-renewal of the
license would also result in significant socioeconomic impacts in New
Hanover County and beyond. These would include loss of direct and
indirect employment as well as reduction in tax revenues to surrounding
jurisdictions. The environmental impacts of the D&D activities would be
assessed during NRC review of a detailed D&D plan prepared by GE
following a thorough site survey.
Agencies and Persons Consulted
During the preparation of the EA, NRC coordinated with various
state and local agencies to inform them about NRC's ongoing review and
to gather information. These contacts included the North Carolina
Department of Environment, Health, and Natural Resources (NCEHN),
Nongame and Endangered Species Section and the NCEHN Division of
Radiation Protection for information on NPDES permit compliance and the
NC Environmental Sampling Program. The NCEHN Division of Water Quality
and the Division of Air Quality in Wilmington, the United States
Environmental Protection Agency (USEPA) Region IV Superfund Remedial
Branch, and the USEPA Toxics Management Division, Air and Radiation
Technical Branch were also contacted.
Finding of No Significant Impact
The NRC has prepared an EA related to the renewal of Special
Nuclear Materials License SNM-1097. On the basis of this assessment,
the NRC 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 EA and the documents related to this proposed action are
available for public inspection and copying at the NRC's Public
Document Room at the Gelman Building, 2120 L Street NW, Washington, DC.
Opportunity for a Hearing
Any person whose interest may be affected by the renewal of this
license may file a request for a hearing. Based on the EA and
accompanying safety evaluation, NRC is preparing to renew License SNM-
1097. Prior to renewing the license, NRC will determine that GE has
satisfied the requirements of the Atomic Energy Act of 1954, et seq.,
and NRC requirements. Any request for a hearing must be filed with the
Office of the Secretary, U.S. Nuclear Regulatory Commission,
Washington, D.C., 20555, within 30 days of the publication of this
Notice in the Federal Register; must be served on the NRC staff
(Executive Director for Operations, One White Flint North, 11555
Rockville Pike, Rockville, MD 20852); and on the licensee (GE Nuclear
Energy Production Facility, P.O. Box 780, Wilmington, NC 28402); and
must comply with the requirements for requesting a hearing set forth in
the Commission's regulation 10 CFR 2, Subpart L, ``Informal hearings
Procedures for Adjudications in Materials Licensing Proceedings.''
The requestor must address the following requirements in detail:
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 area 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 (e.g., 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 6th day of May 1997.
For the Nuclear Regulatory Commission.
Michael F. Weber,
Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards,
NMSS.
[FR Doc. 97-12365 Filed 5-9-97; 8:45 am]
BILLING CODE 7590-01-P
