[Federal Register Volume 61, Number 192 (Wednesday, October 2, 1996)]
[Notices]
[Pages 51470-51473]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-25175]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 40-6940]
Finding of No Significant Impact and Notice of Opportunity for a
Hearing, Renewal of Source Material License SMB-920, Cabot Performance
Materials Boyertown, PA
The U.S. Nuclear Regulatory Commission is considering the renewal
of source Material License SMB-920 for the continued operation of Cabot
Performance Materials (CPM) facility located in Boyertown,
Pennsylvania. CPM processes tin slags, tantalite, and columbite ores to
extract tantalum and niobium. The ores and slags contain uranium and
thorium, and sludges resulting from the slag and ore processing contain
in excess of 0.05 percent uranium and thorium. Therefore, the sludges
are source material as defined and regulated by 10 CFR Part 40, and
their possession by CPM is licensed by the Nuclear Regulatory
Commission.
Summary of the Environmental Assessment
Identification of the Proposed Action
The proposed action is the renewal of CPM's source material license
for five years. With this renewal, CPM will continue to operate the
Boyertown facility to process tin slags, tantalite, and columbite ores,
and will revise their process to use the stored sludges as supplemental
feedstock in addition to new ores and ore concentrates. CPM is licensed
to possess and use up to 400 tons of elemental uranium and thorium in
slag, ores, and sludges.
Need for the Proposed Action
CPM performs a necessary service for the commercial electronics
industry by extracting tantalum and niobium from slag and ores. Denial
of the license renewal application is an alternative available to the
NRC, but would require expansion of tantalum and niobium production
capacity at an existing facility or transfer of extraction activities
to a new facility. Denial of the
[[Page 51471]]
application to process the sludges would result in their continued
storage on site.
Effluent Controls and Monitoring
The continued operation of the CPM facility will result in the
continued release of low levels of radioactive constituents and
fluorides. Under accident conditions, the facility could release higher
concentrations over a short period of time. The facility uses a number
of controls to reduce the release of radioactive materials and
fluorides to the environment, and performs monitoring of effluents and
the environment.
The CPM facility produces gaseous, liquid, and solid effluent
streams. Gaseous effluents are controlled by minimizing the amount of
airborne radioactive materials within the plant, and by the use of a
dust collector, baghouse, and stack scrubber on specific processes.
Liquid effluents are controlled by the use of waste water retention
lagoons and treatment systems that reduce the concentration of
radioactive materials prior to discharge to West Swamp Creek. Solid
wastes are managed through a combination of reprocessing, off-site
disposal, and recycling.
Stack scrubber performance is monitored by measuring the
concentration of fluorine in the scrubber water and the flowrate of the
scrubber recycle water. The performance of the gaseous effluent
controls is further evaluated by the environmental air sampling program
described below. Liquid effluents are sampled at the point of discharge
to Swamp Creek, and the samples are analyzed for uranium and other
constituents. Solid wastes are surveyed prior to off-site disposal.
CPM has performed and will continue to perform monitoring to detect
accumulation of radioactive materials in the environment. This
environmental monitoring program samples sediment and surface water in
West Swamp Creek; and air and ground water at locations on or near the
facility. Forage sampling for fluoride, which was performed under the
previous license, will not be performed under the renewed license.
Two new air monitoring stations downwind of the plant were
installed in 1995. Air samples will be collected continuously at these
two locations, and the samples analyzed for radioactivity. In addition,
CPM has committed to perform a temporary air monitoring program using a
mobile air sampler at additional locations near the site boundaries.
The purpose of this mobile sampling is to further assure that the most
significant pathway for air effluents has been identified.
Environmental Consequences of Proposed License Renewal
Implementation of the proposed action, renewal of the CPM license,
involves both beneficial and negative impacts. The beneficial impacts
include support for production of economically valuable electrical
components and processing of the stored sludge into a more stable form.
The associated negative impacts from continued plant operations include
releases to air and surface water from plant operation. Implementing
either the proposed action or the alternative action, non-renewal of
the license, involves decontamination and decommissioning (D&D) of the
facility.
For the proposed action, the handling of materials and normal
operations of the facility will result in the continued release of low
levels of radioactive and non-radioactive constituents. Under accident
conditions, the facility could release higher concentrations of
materials over a short period of time. The facility will eventually be
decontaminated and decommissioned at the end of its useful life, but
the impacts of such decontamination and decommissioning are beyond the
scope of this Environmental Assessment (EA), which deals only with the
potential environmental impact of continued operations.
Normal operations at the CPM facility will involve groundwater
withdrawals, discharges of fluoride and radionuclides to surface
waters, discharges to the atmosphere, and generation of various solid
and liquid waste streams. The impacts of normal operations are both
radiological and nonradiological.
The radiological impacts of the continued operation of the CPM
facility were assessed by calculating the radiation dose to the
maximally exposed individual located at the nearest residence and the
collective radiation dose to the local population living within 80
kilometers (50 miles) of the plant site.
The results of the dose assessments are summarized below, and a
detailed description of the methodology and results is provided in the
appendix to the EA.
Radionuclides which may be released to the environment include
potassium-40 (K-40), uranium-238 (U-238), uranium-235 (U-235), thorium-
232 (Th-232), and their decay daughters, including radon-222 (Rn-222).
The sources of the releases are the main process building (Building
073) stacks, the ore storage pile, the sludge storage mausoleums, and
the liquid waste system lagoons.
Potentially exposed individuals for the atmospheric releases are
primarily residents along the northeast and north boundaries of the
site. Atmospheric dispersion analysis established that the maximally
exposed individual would be located on the northeast boundary of the
site.
Liquid effluents are released into West Swamp Creek, a tributary of
the Schuylkill River. Because of its low and irregular flow, West Swamp
Creek is not a drinking water supply for area residents. Therefore, the
analysis assumed that an individual along the Schuylkill River, and the
surrounding population out to a distance of 80 kilometers (50 miles),
used this potentially contaminated water.
The radionuclide doses were estimated using the Hanford
Environmental Radiation Dosimetry Software System GENII computer code,
except for radon. 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, and irrigated crops; and external exposure during
recreational activities. Because GENII does not simulate radon
inhalation impacts, the NRC staff developed independent dose estimates
using dose factors specific to radon-222. Details on the method of
radiological impact analysis are presented in the appendix to the EA.
Potential radiation doses from releases to the atmosphere from the
CPM facility are calculated for the maximally exposed individual and
the population. These doses are expressed in terms of the 50-year
committed effective dose equivalent (CEDE) from internal exposure from
the intake of radionuclides for a period of one year. For the maximally
exposed individual, the CEDEs for combined releases from Building 073
and the ore storage pile were estimated as 6.5 x 10 -7 Sv/yr
(0.065 mrem/yr), while the CEDE for release from the storage mausoleums
was estimated as 2.5 x 10 -5 Sv/yr (2.5 mrem/yr). The doses are a
small fraction of background doses for both the maximally exposed
individual and other members of the population; the external background
radiation doses from cosmic and terrestrial sources are approximately
2.6 x 10 -4 and 2.8 x 10 -4 Sv/yr (26 and 28 mrem/yr),
respectively. The doses from atmospheric releases are also a fraction
of the 10 mrem/year limit set by 40 CFR 61 Subpart I, National
[[Page 51472]]
Emissions Standards for Radionuclide Emissions from Facilities Licensed
by the Nuclear Regulatory Commission.
Potential impacts for the maximally exposed individual and the
population from releases to surface water were also calculated. The
largest tissue doses are to the bone surface from ingestion of lead-210
(Pb-210), and external doses are a factor of 10,000 smaller than
internal doses. The CEDE for the maximally exposed individual was
estimated as 2.8 x 10-6 Sv/yr (0.28 mrem/yr). For both the
maximally exposed individual and other members of the population, doses
are a small fraction of background sources.
The NRC regulations (10 CFR 20.1301) require that the Total
Effective Dose Equivalent (TEDE) for members of the public not exceed
1.0 x 10-3 Sv (100 mrem) per year. The TEDE is the sum of the
effective dose equivalent (EDE) from exposure to external radiation for
one year and the CEDE defined above. For atmospheric releases of
radionuclides other than radon, Environmental Protection Agency (EPA)
regulations (40 CFR Part 61, Subpart I) require that the annual
effective dose equivalent not exceed 1.0 x 10-4 Sv (10 mrem).
Doses from CPM facility operations are dominated by releases to the
atmosphere. For the maximally exposed individual, the annual TEDE
including dose from radon was estimated as 2.6 x 10-5 Sv (2.6
mrem). The largest annual tissue dose was estimated as 2.1 x 10-4
Sv (21 mrem) to the lung. This tissue dose is entirely due to radon
releases from the storage mausoleums, which would be eliminated by
implementing the planned sludge processing modifications. Estimated
doses for all other releases are small fractions of applicable limits.
Continued operation of the facility is expected to have minor
impacts on air quality, surface water, ground water, land use, and
biota. Surface water, sediment, and groundwater monitoring during
previous operations have indicated no significant impact from non-
radiological constitutents, including fluoride. It is expected to have
little or no impact on cultural resources, and to have a positive
socioeconomic impact.
Normal operation of the CPM facility is not expected to have a
significant effect on off-site nonradiological air quality, although
fluoride concentrations measured in air have exceeded the State of
Pennsylvania 24-hour maximum of 5 g/m \3\ on occasion. State-
issued operating permits for processing activities include release
limits for compounds of fluorides, and the State's compliance and
enforcement program addresses any exceedence of the limits.
The primary potential impact on terrestrial resources is from
fluoride released to the environment from the ore digestion process.
Biannual monitoring of both corn and grasses since 1988 indicates that
operation of the facility has resulted in elevated fluoride
concentrations in forage crops growing adjacent to the plant.
There are no state or federal standards for fluoride concentration
in forage. While there has been research in this area, as reported in
the EA, no specific regulatory limits are currently applied to this
aspect of the environment. Additionally, there are no federal ambient
air quality standards for fluoride. There has been no increased
degradation in off-site vegetation from fluoride since the previous
assessment, and the expected releases will be the same as or less than
those from previous operations. Therefore, no adverse impacts to the
off-site environment are expected from the continued operation of the
facility.
The handling, processing, and storage of material containing
radioactive constituents at the CPM facility could result in
uncontrolled release of radioactive material to the environment in the
event of an accident. The relatively small quantities and low
concentrations of the radioactive constituents constrain the
radiological impacts of potential accidents. Use of hazardous chemicals
in operations at the facility could also result in uncontrolled
releases, posing a potential risk to workers and public health and
safety.
The accident analysis identified potential hazards, reviewed
potential accident initiators and release mechanisms, developed
accident scenarios, and estimated consequences for a set of potential
accident scenarios. The hazard review identified the primary hazards as
radionuclides in the feed material, process equipment, and sludge
storage mausoleums, and the hazardous chemicals stored on site. For
radioactive material in solid form, the primary release mechanisms
would be drop and resuspension during transfer, and failure of the
filtration systems during processing. For radioactive material in
liquid solution, the primary release mechanism would be equipment
failure during processing and transfer. For hazardous chemicals, the
failure of storage equipment is the scenario with the largest potential
impact. Based on the above considerations, a feed ore spill during
transfer, a large-scale leak of treated liquid radioactive waste, and
release of anhydrous ammonia from tank storage were selected as
representative accidents.
Feed ore is transferred to process equipment from a storage pile
located near building 073. Equipment failure or improper operation
could lead to inadvertent dumping of the load, resulting in an airborne
release of 0.066 and 0.009 Ci of U-238 and Th-232,
respectively. Based on dispersion analysis, the maximally exposed
individual would be 205 meters (673 feet) northeast of building 073,
and the CEDE for this release was estimated as 4.0 x 10-7 Sv (0.04
mrem), indicating insignificant risk to public health and safety.
Approximately 30,280 liters (8,000 gallons) of liquid radioactive
waste are processed daily at the CPM facility. Radionuclides are
removed as filtered solids during processing, and the resulting liquid
is mixed with other liquid streams to generate an overall average daily
flow of approximately 378,500 liters (100,000 gallons). The largest
capacity tank in the system is a 378,500-liter (100,000 gallon) tank
for storing treated liquid. Failure of this tank with release to
surface water bounds potential accidents associated with the waste
treatment system. The released liquid would be diluted in West Swamp
Creek and the Schuylkill River, and the maximally exposed individual
could receive a CEDE of 5.8 x 10-9 Sv (5.8 x 10-4 mrem).
This dose is a very small fraction of normal background radiation,
indicating insignificant risk to public health and safety.
Ammonia is stored under pressure as a liquified gas in a 37,850-
liter (10,000 gallon) tank located on the southeast side of County Line
Road. Failure of a transfer or relief line could cause an uncontrolled
release with potential health and safety impacts. This event was
represented as development of a 2.5-centimeter (1 inch) diameter hole
in the tank vapor space, with isentropic escape through the hole. Under
the assumed conditions, the release rate was estimated as 930 grams per
second (2.05 pounds per second). The release time with no operator
response could be as long as 6 hours. Dispersion analysis established
that the maximally exposed individual would be located 330 meters
(1,083 feet) north-northeast of the release point. Ambient ammonia
concentrations were estimated as 1.3 grams per cubic meter (930 parts
per million) at the location of the maximally exposed individual.
Ammonia concentrations above 1,000 parts per million for an extended
period of time can be lethal, while concentrations
[[Page 51473]]
between 25 and 200 parts per million produce transient irritation. The
potential for this release to occur for an extended period of time is
low because CPM would take response actions in accordance with their
Preparedness, Prevention, and Contingency Plan.
Alternative to the Proposed Action
An alternative to the proposed action is non-renewal of the
license. In this case, CPM would shut down the processes that involve
source material, and would decontaminate and decommission (D&D) the
site in accordance with an approved plan. Cabot would do a thorough
survey of the site grounds and buildings and prepare a detailed D&D
Plan. The environmental impacts of the D&D activities would be assessed
during NRC review of the detailed D&D Plan.
Agencies and Persons Consulted
During the preparation of the EA, various state and local agencies
were contacted for gathering information. These contacts included the
Tri-County Area Chamber of Commerce for employment information, the
Pennsylvania Department of Conservation and Natural Resources for
threatened and endangered species information, the Pennsylvania
Department of Environmental Protection for air quality information, and
the Pennsylvania Registry of Historic Places for cultural resources
information.
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 license 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 whole body dose received by the
maximally exposed individual is below federal regulatory limits.
Finding of No Significant Impact
The NRC has prepared an EA related to the renewal of source
Material License SMB-920. 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.
Opportunity for a Hearing
Any person whose interest may be affected by the renewal of this
license 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, 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 (Cabot
Performance Materials, County Line Road, Boyertown, PA 19512); and must
comply with the requirements for requesting a hearing set forth in the
Commission's regulation 10 CFR Part 2, Subpart L, ``Informal Hearings
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 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 25 day of September 1996.
For the Nuclear Regulatory Commission.
Robert C. Pierson,
Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards,
NMSS.
[FR Doc. 96-25175 Filed 10-1-96; 8:45 am]
BILLING CODE 7590-01-P
