[Federal Register Volume 64, Number 169 (Wednesday, September 1, 1999)]
[Notices]
[Pages 47872-47877]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 99-22767]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 40-08980]
Environmental Assessment, Finding of No Significant Impact, and
Notice of Opportunity for a Hearing for Remediation of the Lakehurst,
NJ Site
Summary and Conclusions
The environmental assessment (EA) reviews the environmental impacts
of the decommissioning actions proposed by Heritage Minerals,
Incorporated (HMI) of their Lakehurst, New Jersey facility. Based upon
the NRC staff evaluation of the HMI Final Status Survey Plan (FSSP),
dated November 3, 1997, it was determined that the proposed
decommissioning can be accomplished in compliance with the NRC public
and occupational dose limits, effluent release limits, and residual
radioactive material limits. In addition, the approval of the proposed
action, i.e., decommissioning of HMI's Lakehurst, New Jersey facility
in accordance with the commitments in NRC license SMB-1541 and the FSSP
(decommissioning plan), will not result in significant adverse impact
on the environment.
1.0 Introduction
1.1 Background
Heritage Minerals, Inc. is the current holder of NRC radioactive
source materials license SMB-1541 (NRC Docket 40-08980) for the
possession of radioactive material resulting from operations at their
facility located in Lakehurst, New Jersey. The license authorizes HMI
to possess at any one time a maximum of 300 kg of uranium in the form
of natural uranium as monazite and 15,000 kg of thorium in the form of
natural thorium as monazite. Processing of licensed material is not
authorized except incident to facility decommissioning activities and
packaging materials for shipment.
In December 1996, HMI informed the NRC staff that it intended to
decommission the Lakehurst, New Jersey facility. The licensee submitted
the Final Status Survey Plan (FSSP or decommissioning plan) to the NRC
for review on November 3, 1997. The license was renewed on May 26, 1998
to authorize possession, packaging, storage, and decommissioning in
accordance with the FSSP and transfer of products and waste to
authorized recipients. Prior to the renewal, a safety evaluation report
(SER), which evaluated conformance of the proposed action with NRC
regulations and regulatory guidance was prepared and the opportunity
for a hearing was publicly noticed in the March 12, 1998, Federal
Register Notice (63 Federal Register 12114). In response to NRC
requests, in 1998-99, HMI provided additional information to clarify
certain planned remediation activities. The NRC is considering a
license amendment which include additional HMI commitments during
facility decommissioning.
1.2 Purpose and Need for Proposed Action
NRC is considering approval of the FSSP to allow Heritage Minerals,
Inc. to remove radioactive material attributable to licensed operations
at the site, to levels that permit release of the property for
unrestricted use and termination of radioactive source materials
license SMB-1541.
1.3 Description of Proposed Action
The objective of HMI is to decontaminate and decommission the
Lakehurst, NJ facility to permit release for unrestricted use and
termination of NRC license SMB-1541. Decommissioning will involve
remediation of buildings and other above-grade structures,
decontamination of process equipment and sumps, excavation of soil
containing monazite sands, and restoration of excavated areas. Soil and
other radioactively contaminated materials will be transported to
either a licensed disposal facility or recipient authorized to receive
such material.
NRC staff reviewed the information provided by HMI in the FSSP
describing the proposed decommissioning actions and, by letter dated
March 16, 1999, requested additional information regarding specific
areas that needed clarification. NRC staff concluded that the
decommissioning plan (FSSP) and supplemental information (letters dated
November 30, 1998, June 24, 1999, July 13, 1999 and August 17, 1999)
from A.J. Thompson, Attorney for HMI, Inc., responding to NRC comments
provided an adequate information base for assessing potential
environmental impacts from the proposed action.
2.0 Facility Description/Operating History
2.1 Site Locale and Physical
Description The Heritage Minerals, Inc. site is located on Route 70
in Lakehurst, Manchester Township (Ocean County), New Jersey, in the
Atlantic Coastal Plain. It encompasses an area of approximately 7000
acres, of which 1000-1200 acres were used for mining operations
involving monazite.
[[Page 47873]]
Other areas remained undisturbed. The plant and production areas
including mill tailings containing monazite (produced as a result of
previous operations) occupied an estimated 500 acres. The monazite pile
is located within a security fence and occupies approximately 700 cubic
meters. Areas adjacent to the site are predominantly rural, with bands
of existing or recently developed residential communities within
Manchester Township.
In the Hydrogeologic Investigation Report prepared for HMI,
Fellows, Read, & Associates, Inc. (1989) characterized the geology and
hydrogeology of the facility. Geologic deposit formations consist of
underlying sediments of stratified clay, silt, sand, and gravel on
well-indurated bedrock. The topography is relatively flat, recontoured
by surface mining of ilmenite surface deposits. Wetlands form the
drainage of adjacent Wrangel Brook, which has an easterly streamflow.
Two lakes were created along the Green Branch of Wrangel Brook as a
result of mine dredging operations.
Groundwater flow occurs from areas located north and west of the
site to east and northeast towards the tributaries of the Toms River.
The Toms River and its tributaries represent the major groundwater
discharge zones for the region. Local groundwater flow is from upland
areas to lower areas where groundwater discharges to streams and
wetlands. Site groundwater is recharged by precipitation and flows
unconfined through underlying sands. The Green Branch, Michaels Branch,
and Davenport Branch of Wrangel Brook serve as local discharge zones
for shallow ground water, with subsequent discharge to the Toms River
or Barnegat Bay.
2.2 Descriptions of Facility Operations
Between 1973 and 1982 the site was operated by ASARCO, Inc., for
dredging and processing sand deposits to extract heavy minerals. The
titanium mineral, ilmenite, was the primary mineral recovered by
various physical separation methods. There was no chemical separation
involved in the extraction and concentration processes. Heavy minerals,
including monazite were pumped as slurry to a Wet Mill. At the Wet
Mill, the heavy minerals were separated from the slurry, then
stockpiled for dewatering, while the lighter fraction was returned to
the dredge pond. The heavy mineral concentrate was heated in a Dry
Mill, then screened to remove coarse material. The high conductivity of
the titanium dioxide bearing minerals allowed electrical separation
from other heavy minerals. Further magnetic refinement produced the
final ilmenite product. The dry mill tailings containing essentially
all the monazite from the heavy minerals concentrate were mixed with
water and pumped to an area east of the dry mill building.
ASARCO ceased operations in 1982. Evaluation of residual materials
by private companies for commercial use continued until the property
was purchased by HMI in 1986. Plant facilities were leased to Mineral
Recovery, Inc. (MRI), who performed operational testing for titanium
recovery until 1987.
HMI assumed property control, conducting site operations under NRC
license until 1990 when all production stopped. Operations were
comparable to the ASARCO process, utilizing dry mill tailings as feed
material. The tailings were mixed with water, pumped to the wet mill
for mineral separation according to their conductive properties,
proceeding through a dewatering and drying process. Minerals were
recovered and sold as leucoxene and rutile (titanium dioxide products)
and zircon. Licensable amounts of monazite were present throughout the
electrical and magnetic separation processes. In early 1990, processing
of feed materials continued followed by recycle of tailings from the
MRI operations. Mill tailings containing monazite were deposited in a
stockpile east of the dry mill. Due to economic conditions, HMI
terminated all operations in August 1990. Approximately 700 cubic
meters of stockpiled tailings remain licensed to HMI.
3.0 Radiological Status of the Facility
3.1 Structures and Equipment
HMI performed decontamination of building surfaces and disposed of
contaminated equipment in 1990-1991. Subsequent radiation (screening)
surveys were conducted of the interiors of the wet mill and dry mill.
Process trains within each building were characterized according to
their monazite content and operating history as affected or unaffected
areas using NUREG/CR-5849, ``Manual for Conducting Radiological Surveys
in Support of License Termination'' criteria. The methods used to
dismantle and decontaminate process equipment in affected areas and for
disposition of resultant materials are described in the FSSP. The same
methods will be used for decontamination of building interiors prior to
the final radiological survey and will serve as the basis for
termination of NRC Source Material License SMB-1541.
The final release status surveys described in the FSSP will be
performed in accordance with NUREG/CR-5849 criteria. Residual
radioactive materials that exist in affected areas will meet current
guidelines described in ``Guidelines for Decontamination of Facilities
and Equipment Prior to Release for Unrestricted Use for Termination of
Byproduct, Source, and Special Nuclear Material Licenses,'' (U.S.
Nuclear Regulatory Commission, Policy and Guidance Directive FC 83-23,
1983). Details regarding the radiological status of affected areas
within the Wet and Dry Mill buildings are described in the next
sections. At present, contaminated material containing monazite is
being stored in the outdoor tailings pile. A final survey of affected
areas will be required by NRC after residual material is removed and
decontamination is complete.
Following review of the Heritage Minerals, Inc. site radiological
characterization of structures and equipment, the NRC staff finds
characterization was performed in accordance with NUREG/CR-5849. The
NRC staff review of the FSSP also finds it adequate for remediating
structures and equipment to radiological levels below the NRC
guidelines for unrestricted release (Nuclear Regulatory Commission,
1983). The staff concludes no adverse environmental impacts will result
from planned remediation of the site structures and equipment.
3.1.1 Wet Mill Building. The Wet Mill Building process equipment
used to extract product materials from raw feed was grouped into
affected and unaffected survey units. The majority of survey units
including floors, lower walls, and western mill areas are unaffected.
Mechanical separation units and feed sumps involving transfer or
processing of product material containing monazite were identified in
the FSSP as affected areas. Final radiological surveys of interior
surfaces will be within allowable release limits for natural thorium,
the primary contaminant of concern. Prior to release of equipment in
affected areas for unrestricted use, the NRC release limit of 1,000
dpm/100 cm2 for average surface contamination and maximum release limit
of 3,000 dpm/100 cm2 will be met.
3.1.2 Dry Mill Building. Equipment in the Dry Mill Building was
used to extract product materials from the Wet Mill process feed.
Consistent with Wet Mill Building survey units, Dry Mill Building
equipment was also grouped into affected and unaffected areas. Most
[[Page 47874]]
areas of the Dry Mill involving monazite including floors, ceiling, and
lower walls (up to two meters above floor level) are affected. These
include dryers, high tension separators, and sumps. NRC surface
contamination release limits are the same as those used for Wet Mill
equipment.
3.2 Surface and Subsurface Soils
Radionuclide concentrations and direct radiation levels for surface
and subsurface soils at the facility have been measured in the Wet
Mill, Dry Mill, dust collectors, tailings (monazite) pile, and at
various outdoor locations.
Direct radiation levels inside buildings and outdoor areas were
routinely measured by HMI personnel since 1990. Direct gamma exposure
rates at ground level and 1 meter above the surface were reported for
the monazite pile and areas in and around the Wet and Dry Mills.
Average monazite pile perimeter readings ranged between 300-1700
R/hr up to 2000 R/hr on the pile. Readings at outdoor
locations around buildings were at or near background levels. The
highest exposure rates were measured on storage drums located inside
the security fence surrounding the pile, at levels up to 3000
R/hr. Small amounts of residual material (unlicensed) exists
from recycled ASARCO tailings deposits in adjoining owner controlled
property locations. These areas showed direct gamma radiation readings
ranging between 10-150 R/hr and will not be included in the
remediation. Normal background radiation levels for other facility
production areas is 7-20 R/hr.
In July 1996, Radiation Science, Inc. issued a Report of Site
Background for HMI which included soil samples at a depth of six inches
from undisturbed environment, representative of natural site
conditions. Background levels were established by performing gamma
spectral analysis for U-238 and Th-232 on 32 samples. Mean values
reported for background samples was 0.31 pCi/gm for U-238 concentration
and 0.25 pCi/gm for Th-232 concentration. Average dose rates
measurements from areas where samples were taken was 3.0 R/hr.
Sample analysis of soils taken from recycled tailings, an unused
settling pond, plant tailings, and new feed materials did not exceed
NRC limits for total uranium and thorium (i.e., 10 pCi/g above
background) for unrestricted release. Only soil in the monazite pile
was measured above licensable source material quantities, and showed
total concentrations of Ra-226 and Ra-228 up to 1376 pCi/gm. The FSSP
identifies these soils as the material to be considered for remediation
activities.
Following review of the HMI site radiological characterization
studies for soils, the NRC staff finds the characterization effort and
FSSP adequate for determining areas of elevated radioactivity in soils
that require remediation to limit concentrations to the NRC limits for
unrestricted release (46 Federal Register 52061-52063).
3.3 Surface Water and Groundwater
Analyses for radioactivity of surface water samples collected from
existing site monitoring wells and offsite streams were reported by
Camp Dresser & McKee, Inc. in 1997 as part of the Mine Tailings
Radiological Assessment Plan prepared for the New Jersey Department of
Environmental Protection. Concentrations measured for groundwater
samples were 2.0-7.0 pCi/l for gross alpha and under 2.0-5.0 pCi/l for
gross beta. Results of surface water samples were 2.0-3.9 pCi/l gross
alpha and 2.0-4.2 pCi/l gross beta. Due to the insoluble properties of
monazite and generally low levels of radiological contamination
identified in samples, no concern was found regarding dissolution of
radioactivity into groundwater and surface water.
Following staff review of the characterization of surface waters
and groundwater around the HMI site, the NRC staff concludes the
characterization is adequate and radiological contamination of surface
waters and groundwater is below levels that would be a concern for
environmental impacts.
3.4 Air
HMI reported results from 1990 air sampling measurements in three
locations of the Dry Mill taken by their contractor, Teledyne Isotopes.
Air filters were analyzed for gross alpha activity using an alpha
scintillation counter. Activity detected was assumed to be Th-232, with
reported concentrations less than 1.6 x 10-12 Ci/
ml. These concentrations were less than effluent concentrations limits
allowed in 10 CFR Part 20, Appendix B, and are therefore found by NRC
to be below levels that could lead to adverse environmental impacts.
Dust and security control measures provide confidence that air quality
will not be degraded during decommissioning activities to levels that
exceed NRC limits in 10 CFR Part 20.
4.0 Evaluation of Proposed Methods for Decontamination and
Dismantlement of Structures, Buildings, and Equipment
4.1 Decontamination of Buildings, Equipment, and Outdoor Areas
HMI's proposal for decontamination of buildings, equipment, and
outdoor areas is provided in the FSSP, supplemented by additional
letters clarifying remediation activities in response to NRC's request
for additional information. In 1991, process equipment, Wet and Dry
Mill buildings, and survey units with operating equipment suspected to
contain radioactive material were cleaned and decontaminated.
Decontamination methods used for mill equipment included high pressure
washing, steaming, general wipe down and scrubbing, blowing, and
dusting and sweeping of surfaces. Radiation surveys of buildings and
areas around the monazite pile have been performed routinely by HMI
since that time.
The FSSP describes the proposed decommissioning activities and
methods for protecting workers and the public during removal of
monazite contaminated soil. Residual radioactivity remaining inside
buildings is confined to fine sand grains present on equipment
surfaces. Affected survey units may require further decontamination
prior to performing the final status survey. Areas that contain only
loosely adhered contamination will be HEPA vacuumed to remove
contaminants. Fixtures, tanks, pumps, high tension separators, piping,
and heavy equipment will be isolated, disassembled, and decontaminated
as necessary, then resurveyed prior to release for unrestricted use.
Equipment that cannot be economically decontaminated will be
resurveyed, and all equipment with contamination above the NRC limits
for unrestricted release or equipment suspected to contain radioactive
material will be treated as radioactive waste.
When removal of process equipment from mill buildings is completed,
building characterization surveys will be conducted. Walls up to two
meters and floors are to be surveyed in accordance with the FSSP. Those
buildings that contain residual contamination will be decontaminated
below NRC guideline values using the most economical and reliable
methods available. HMI's objective is to free release all buildings
above grade to allow demolition (if deemed necessary) of clean
buildings. Decontamination of ground-level floors will include the top
surface of the concrete slabs, if needed.
[[Page 47875]]
Material from demolition of ground-level floors and underlying soils
will be surveyed for contamination and remediated.
Surface and subsurface soils with Th-232 concentrations greater
than 10 pCi/g is restricted to the monazite pile. HMI proposes two
excavations of materials with monazite concentrations greater than 10
pCi/g above background. Contaminated soil (monazite ore) will be
excavated, placed into a hopper, and transferred to shipping
containers. This will be followed by a second excavation of surface
layer soil to be removed in a similar manner. A fenced security area
near the existing pile will be established for staging of shipping
containers and contaminated equipment prior to transportation off-site.
After the second excavation, area radiation levels are expected to be
reduced to no more than twice background. Excavation of soil to meet
Th-232 cleanup criteria will also serve to remove residual uranium
contamination because both contaminants are contained in the monazite-
rich soil. Once remediated, the remaining soil will be resurveyed in a
manner consistent with NRC-accepted methods to ensure residual thorium
and uranium contamination meet the NRC unrestricted release criteria.
Soil and other material will be transported from the site either to a
licensed disposal facility or exported under NRC Export License
XSOU8751, issued to HMI on May 2, 1997.
Under Condition 15 of Materials License SMB-1541, HMI cannot
release for unrestricted use areas within plant buildings or the
monazite pile without specific, written authorization from the NRC.
Based on the NRC review of building and equipment decontamination
methods described in the FSSP and supporting documents, NRC concludes
that the methods are adequate for ensuring that equipment, buildings,
and outdoor areas will meet the NRC guidelines for unrestricted use and
no adverse environmental impacts will result from planned activities.
5.0 Decommissioning Alternatives and Impacts
5.1 No Action
No decommissioning action by HMI would constitute a violation of 10
CFR 40.42(d) requirements, which requires that licensees begin site
decommissioning of buildings and outdoor areas that contain residual
radioactivity after permanently ceasing principal activities. Impacts
of the no-action alternative are maintaining an NRC license, which
would significantly reduce options for future property use, and require
perpetual care and security of the site in its current radiological
condition to prevent radiation exposure to monazite contamination and
unauthorized public access.
5.2 Proposed Action
The proposed action is the approval to implement the Heritage
Minerals, Inc. Final Status Survey Plan, for decommissioning activities
at the Lakehurst, New Jersey facility that will permit unrestricted use
of the site and termination of License No. SMB-1541. Decommissioning
the facility for unrestricted release allows productive use of the land
in the future. Site remediation is expected to mitigate potential
future environmental impacts attributable to existing radiological
contamination resulting from past operations.
5.3 Alternatives to Proposed Action
Two alternatives to the proposed action are considered. The first
alternative is to not release the site for unrestricted use and keep
the property under license. This alternative is unfavorable because
maintaining an NRC license for the site would provide negligible, if
any, environmental benefit, but would greatly reduce options for future
use of the property. The second alternative involves storage of
excavated soils on-site for an indefinite period should HMI be unable
to export or transfer the material for disposal. While on-site storage
defers the costs associated with disposal at a licensed facility, it
removes the property from productive use, resulting in a negative
impact to the economic potential of the local area.
The NRC determines the proposed action to be more favorable than
either no-action or alternatives to the proposed action.
6.0 Radiation Protection Program
6.1 Radioactive Waste Management and Transportation Program
The radioactive waste management program at the HMI site includes
identification, characterization, segregation, packaging, labeling,
manifesting, and transporting waste in accordance with NRC, U.S.
Department of Transportation (DOT), and other applicable federal,
state, and local regulations. Included as contaminated radioactive
waste materials from decommissioning activities will be equipment,
tools, process material, building debris, decontamination materials
(rags, wipes, filters), decontamination waste, soils, residual process
equipment waste (sludges), and used personal protective equipment.
Since HMI intends to comply with all applicable requirements, NRC
finds the planned radioactive waste management and transportation
programs adequate for the materials at the site, and no adverse
environmental impacts are expected from waste management activities or
transfer of the material offsite.
6.2 Technical and Environmental Specifications
6.2.1 Unrestricted Use Guidelines. Guidelines for unrestricted use
for natural thorium and uranium for the Heritage Minerals, Inc. site
are Option 1 in the 1981 Branch Technical Position on ``Disposal or
Onsite Storage of Thorium or Uranium Wastes From Past Operations'' (46
FR 52061), and NRC ``Guidelines for Decontamination of Facilities and
Equipment Prior to Release for Unrestricted Use for Termination of
Byproduct, Source, and Special Nuclear Material Licensees,'' Policy and
Guidance Directive, FC 83-23. The unrestricted release criteria are
identified in the table below.
Soil Release Criterial \1\
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Maximum soil
Radionuclide concentration Reference
(pCi/g)
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Natural Thorium (Th-232 plus Th-228) if all 10 (46 Federal Register 52061-52063).
daughters are in equilibrium.
Natural Uranium Ores (U-238 plus U-234) if all 10 (46 FR 52061-52063).
daughters are present and in equilibrium.
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\1\ If only one radionuclide is present, the maximum concentration is the value listed in this table. If more
than one radionuclide is present, however, the ratio between the measured concentration and the corresponding
limit listed in this table is determined. The sum of such ratios for all radionuclides present must not exceed
one.
[[Page 47876]]
6.2.2 Radiological Health and Safety Program. HMI will select a
decommissioning contractor who will follow radiation protection
procedures sufficient to administer the radiation protection program
authorized by License SMB-1541. The radiation protection program has
been routinely inspected by NRC staff and found to be well implemented.
The proposed action is limited in scope and not expected to include
unique health and safety issues outside the scope of the radiation
protection program. NRC will conduct site inspections while
decommissioning activities are in progress. NRC determines the
radiation protection program adequate for the proposed action.
6.2.3 Corporate Organization and Management. The HMI site manager
will function as the licensee representative of the decommissioning
project to provide oversight for all project activities. The site
manager's function is to coordinate scheduling and status reports with
the contractor Project Manager (PM) and HMI legal advisor. The PM will
maintain overall responsibility for performance of project operations
for the duration of the project until decommissioning activities are
completed. The PM and decommissioning workers report directly to the
HMI technical and legal staff for all project related activities,
management direction, and resolution of operational issues. Primary
responsibility of the PM includes on-site workforce management to
ensure agreed to work schedules are met. The HMI Radiation Safety
Officer (RSO) will report to the site manager and continue to perform
oversight of all radiological work-related activities throughout the
decommissioning project.
From review of job descriptions and responsibilities involved in
radiological safety during decommissioning, NRC determines that the
designated functions are acceptable to implement the radiological
safety program during proposed decommissioning activities.
6.2.4 Radiological Exposure Control. Areas where radioactive
materials are used and stored will be posted to control exposures to
workers and visitors and avoid the spread of contamination. Measures to
be taken to ensure control of contamination include donning of anti-
contamination clothing, personnel monitoring, and frequent area
radiation surveys. External radiation monitoring will be conducted
through the use of environmental dosimeters placed at strategic
locations around the monazite pile and work areas. The need for and
type of dosimetry for workers and visitors in radiologically controlled
areas will be determined by the contractor, and may include issuance of
a radiation work permit. The primary dosimeter will be the
thermoluminescent dosimeter (TLD) for whole body exposure, however,
other types such as extremity TLD's will be employed, as conditions
warrant.
For activities that have the potential to generate dusts, airborne
particulate monitoring will be performed to demonstrate compliance with
10 CFR Part 20 intake limits, determine whether precautionary measures
are needed (engineering controls, use of respiratory equipment), and
show how exposures are being maintained ALARA. To reduce the amount of
airborne particulates during excavations, the monazite pile will be
sprayed with water twice per day. For equipment decontamination within
affected survey units, HEPA air filtration in the immediate work area
will be used, as needed.
Resuspension and airborne transport of contaminated soil during
excavations serves as the primary pathway for off-site releases from
decommissioning activities. HMI proposes to measure air particulates in
the downwind direction through the use of a high-volume air sampler.
Workers involved in excavations will be required to wear respiratory
protection until radiological airborne activity levels are determined.
HMI does not expect the proposed action will result in the generation
of off-site, airborne concentrations that would result in dose to a
member of the public in excess of the dose limits in 10 CFR Part 20.
Previous results of groundwater and surface water sampling have shown
negligible dose contribution due to the low levels of radionuclides
during site operations. Decommissioning activities will have no further
impact, therefore, additional water sampling is not needed.
HMI's total dose estimates for a worker based on direct gamma
exposure rate from airborne soil releases from excavation activities of
the monazite pile of 1mR/h is 320 mRem, with dust inhalation dose at 6%
of the annual limit of intake (ALI) for the duration of the proposed
action. The off-site (public) annual dose limit in 10 CFR Part 20 is
100 mrem. Given the low estimated exposure beyond the site boundary,
the air sampling is adequate for off-site monitoring of potential
releases to ensure compliance with the dose limits of 10 CFR Part 20.
Following review of radiological exposure controls, NRC determines
the proposed program methodologies are adequate for detecting potential
environmental impacts prior to license termination.
6.2.5 Security. Security of radioactive material at the HMI
facility is maintained by a fence with a locked front entry gate around
the perimeter of the monazite pile. Security for mill buildings is
minimal, and other site areas are left unattended for long periods.
Equipment theft in mill buildings has been a known concern within
buildings, but missing equipment was believed to have been
decontaminated after operations shut down in 1990. These concerns
should be alleviated by the presence of on-site decommissioning
personnel. HMI has committed to establishing a fenced exclusion area
for shipping containers and equipment removed from buildings which
cannot be released for unrestricted use.
NRC determines this is an adequate level of security to ensure
radiological safety will be maintained during decommissioning
activities at the site.
6.3 Radiological Accident Analysis
Potential accident scenarios considered include building fire and
loading or shipping incidents of radioactive materials. Due to the low
potential for fire or explosion in building structures and the limited
quantities of material used during transfer operations, accidental
releases of radioactive materials in quantities that could affect
public health and safety are unlikely. A 24-hour number will be
established to provide Radiation Safety Officer notifications in the
event emergency response is necessary.
The NRC concludes that HMI has adequately addressed the potential
for radiological accidents.
7.0 Environmental Impacts
7.1 Radiological Impacts to the Public and Workers
Potential sources of worker exposure from decommissioning
activities include characterization work, decontamination and
remediation of buildings and associated structures (piping,
foundations), and excavation of soils. Past NRC inspections showed
activities resulted in no measurable internal or external dose to
workers. These activities were similar to the proposed activities and
included equipment and building decontamination, radiological
characterizations, and monazite pile maintenance. NRC dose calculation
based upon excavation and packaging of 700 m3 of monazite
soil at an average thorium soil concentration of 25 pCi/g (highest
sample result obtained during
[[Page 47877]]
NRC inspection) project an occupational worker exposure under 10 mRem,
primarily due to external exposure. Based on the above, the staff
believes that worker exposures will be well within the 10 CFR Part 20
annual worker dose limit of 5000 mRem, and that no adverse impacts to
workers will result.
Potential sources of radiological impacts to the public from
decommissioning activities at the HMI site are similar to those
pertaining to worker exposures (decontamination and excavation dusts),
but require transport over greater distances to reach off-site
receptors. As a result, lower concentrations and doses are expected for
members of the public than for workers. Previous NRC inspections showed
that worker exposures during past activities were undetectable.
Similarly, the public doses from these activities should be
undetectable. The NRC staff has determined that HMI has provided
adequate plans to ensure that potential radiological impacts to members
of the public from the proposed action will not exceed NRC limits and
are unlikely to result in adverse environmental impacts.
7.2 Nonradiological Impacts
There are no planned direct uses of chemicals in the proposed
action, only the excavation of soil, and remediation of equipment and
buildings. No other operations have a potential to affect the
environment. During scoping and characterization surveys, an assessment
of each building will be performed to identify the presence of
hazardous or mixed wastes. The survey will identify items requiring
management of hazardous substances, if found.
The NRC staff has determined that HMI has acceptably addressed the
control of potential releases of nonradiological hazardous materials.
8.0 Agencies and Individuals Consulted
NRC transmitted the FSSP to the New Jersey Department of
Environmental Protection (NJDEP), US Environmental Protection Agency,
Region 2, and Township of Manchester by letters dated February 13,
1998, for review and comment. The response letter of March 18, 1998
from the NJDEP included comments regarding characterization of areas
with thorium levels below licensable quantities and extent of soil
removal, was forwarded to HMI for evaluation. HMI addressed the State's
comments in their letter of November 30, 1998 to NRC providing
acceptable responses to the NJDEP questions. No response was received
from the EPA or Manchester Township. HMI has committed to coordinate
with the NJDEP and comply with applicable State and local regulations
during decommissioning activities.
9.0 Finding of No Significant Impact
The Commission has prepared an EA related to the proposed
unrestricted release, and removal from license SMB-1541, of 700
m3 of monazite-rich soil from the Heritage Minerals, Inc.,
Lakehurst, New Jersey site. On the basis of the EA, the Commission has
concluded that this licensing action would not significantly affect the
environment and does not warrant the preparation of an environmental
impact statement. Accordingly, it has been determined that a Finding of
No Significant Impact is appropriate.
The NRC hereby provides notice that this is a proceeding on a
license amendment falling within the scope of Subpart L, ``Informal
Hearing Procedures for Adjudications in Materials and Operator
Licensing Proceedings,'' 10 CFR Part 2. Pursuant to Sec. 2.1205(a), any
person whose interest may be affected by this proceeding may file a
request for hearing in accordance with Sec. 2.1205 (d). A request for
hearing must be filed within thirty (30) days of the date of
publication of this Federal Register Notice.
The request for a hearing must be filed with the Office of the
Secretary either:
1. By delivery to the Docketing and Service Branch of the Secretary
at One White Flint North, 11555 Rockville Pike, Rockville , MD 20852-
2738; or
2. By mail or telegram addressed to the Secretary, U.S. Nuclear
Regulatory Commission, Washington, D.C., 20555. Attention: Docketing
and Service Branch.
In addition to meeting other applicable requirements of 10 CFR Part
2 of the NRC's regulations, a request for a hearing filed by a person
other than an applicant must describe 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, with particular reference to the factors set out in Sec.
2.1205(h),
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 a hearing is
timely in accordance with Sec. 2.1205(d).
In accordance with Sec. 2.1205(f), each request for hearing must
also be served, by delivering it personally or by mail, to:
1. Heritage Minerals, Inc., Attention: Anthony J. Thompson,
Esquire, ShawPittman, 2300 N Street, NW, Washington, DC 20037-1128; and
2. The NRC staff, by delivery to the Executive Director for
Operations, One White Flint North, 11555 Rockville Pike, Rockville, MD
20852-2738 or by mail, addressed to the Executive Director for
Operations, U.S. Nuclear Regulatory Commission, Washington, DC 20555.
The documents related to this proposed action are available for
public inspection and copying at the NRC Public Document Room, 2120 L
Street NW., Washington, DC 20555 or at the NRC's Region I offices
located at 475 Allendale Road, King of Prussia, PA 19406.
10.0 References
Berger, J.D., ``Manual for Conducting Radiological Surveys in
Support of License Termination,'' NUREG/CR-5849, Washington, DC:
Nuclear Regulatory Commission. 1992.
Nuclear Regulatory Commission, ``Guidelines for Decontamination
of Facilities and Equipment Prior to Release for Unrestricted Use
for Termination of Byproduct, Source, and Special Nuclear Material
Licenses,'' Policy and Guidance Directive FC 83-23, 1983.
Nuclear Regulatory Commission, ``Final Generic Environmental
Impact Statement in Support of Rulemaking on Radiological Criteria
for License Termination of NRC Licensed Nuclear Facilities,'' NUREG-
1496, Volume 2, 1997.
Orlando, D., et al., ``NMSS Handbook for Decommissioning Fuel
Cycle and Materials Licensees,'' NUREG/BR-0241, Washington, DC:
Nuclear Regulatory Commission, 1997.
Dated at King of Prussia, Pennsylvania this 20th Day of August
1999.
For the Nuclear Regulatory Commission.
George Pangburn,
Director, Division of Nuclear Materials Safety.
[FR Doc. 99-22767 Filed 8-31-99; 8:45 am]
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