Environmental Assessment, Finding of No Significant Impact, and Notice of Opportunity for a Hearing for Remediation of the Lakehurst, NJ Site

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\

----------------------------------------------------------------------------------------------------------------

Maximum soil

Radionuclide concentration Reference

(pCi/g)

----------------------------------------------------------------------------------------------------------------

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.

----------------------------------------------------------------------------------------------------------------

\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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