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

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

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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,

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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.

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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]

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