[Federal Register Volume 63, Number 80 (Monday, April 27, 1998)]
[Notices]
[Pages 20671-20673]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-11123]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 70-0734]


Finding of No Significant Impact and Notice of Opportunity for 
Hearing for the Amendment of Materials License SNM-696, General 
Atomics, San Diego, CA

AGENCY: Nuclear Regulatory Commission.

ACTION: Finding of no significant impact and notice of opportunity for 
hearing for the amendment of materials license SNM-696, General 
Atomics, San Diego, CA.

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    The U.S. Nuclear Regulatory Commission is considering amendment of 
Special Nuclear Material License SNM-696, issued to General Atomics 
(the licensee) located in San Diego, California to incorporate a Site 
Decommissioning Plan. The Commission has determined not to prepare an 
environmental impact statement for the proposed action, because the 
amendment will not have a significant effect on the quality of the 
human environment for reasons described in the Environmental Assessment 
(EA).

Summary of the Environmental Assessment

Background

    General Atomics (GA) has been authorized by the U.S. Nuclear 
Regulatory Commission (NRC) and its predecessor, the Atomic Energy 
Commission, to use special nuclear material in nuclear fuel fabrication 
and research and development for more than 30 years. Special nuclear 
material used at the San Diego site included the radioactive materials 
plutonium and uranium enriched in the isotopes uranium-233 and uranium-
235. As operations changed at the site, GA initiated decommissioning 
activities affecting portions of the site beginning in the mid 1980's. 
By the early 1990's, fuel fabrication operations involving special 
nuclear material at the facility had ceased, and in September of 1996, 
GA's Special Nuclear Material License, SNM-696, was amended to 
authorize only activities incident to decommissioning. GA also 
currently has State of California Radioactive Materials License No. 
0145-37 to possess and use source and byproduct materials and NRC 
Reactor Licenses, R-38 and R-67, for two Training Reactor-Isotope-
General Atomics research reactors. By application dated October 11, 
1996, and supplements dated December 5, 1996; April 18, 1997; and 
January 15, 1998; GA requested an amendment to its fuel fabrication 
License SNM-696 to incorporate an overall Site Decommissioning Plan 
(DP).

Identification of the Proposed Action

    The proposed action is the amendment of GA's license to incorporate 
the DP, which describes the remaining decommissioning activities 
planned at the GA facility under License SNM-696 and release of the 
site for unrestricted use. The DP describes the areas and facilities to 
be decommissioned, the decontamination techniques, and the proposed 
effluent control and waste management practices that will be used 
during decommissioning.
    GA intends to decommission to radiation levels required for 
unrestricted use and to terminate License SNM-696 for these areas. Soil 
will be remediated to levels specified in Option 1 of the Branch 
Technical Position (BTP), ``Disposal or Onsite Storage of Thorium or 
Uranium Wastes from Past Operations,'' (46 FR 52061; October 23, 1981). 
Facilities and equipment will be decontaminated to levels specified in 
``Guidelines for Decontamination of Facilities and Equipment Prior to 
Release for Unrestricted Use or Termination of Licenses for Byproduct, 
Source, or Special Nuclear Material,'' (USNRC, Policy and Guidance 
Directive FC 83-23, Division of Industrial and Medical Nuclear Safety, 
November 4, 1983).

The Need for the Proposed Action

    GA is not required to submit an overall site DP because all 
procedures and activities necessary to carry out decommissioning of the 
site have been previously approved by the NRC, consistent with the 
provisions of 10 CFR 70.38(g)(1). However, the incorporation of overall 
site DP into GA's license reduces the administrative effort for both 
the licensee and the NRC by reducing the number of documents which must 
be generated and reviewed. It also facilitates a more consistent and 
organized decommissioning approach across the facility.

Environmental Impacts for the Proposed Action

    The NRC staff performed a radiological dose assessment to estimate 
the impact from airborne radioactive releases under the proposed 
action. Only radioactive effluents were considered because non-
radioactive releases are expected to be insignificant. In addition, 
because liquid effluents were released only through the sanitary

[[Page 20672]]

sewer system, these releases were considered to be insignificant 
compared to airborne releases due to dilution of these discharges prior 
to introduction into any potential drinking water source. Because the 
closest resident is approximately one mile from the facility and any 
discharges would be extensively diluted prior to exposure of the 
resident, the NRC assumed the maximally exposed individual was an on-
site, non-radiation worker. (GA currently leases areas of the facility 
that have been previously released for unrestricted use). The NRC 
assumed this person was exposed 8 hours/day, 40 hours per week, 50 
weeks per year.
    During decommissioning, NRC estimated that the annual average 
release concentrations would be 5 x 10-14 Ci/ml of 
uranium (of various enrichments) and thorium, 1 x 10-13 
Ci/ml of mixed activation and fission products, and 
15 x 10-14 Ci/ml of other radionuclides ranging 
from atomic number 3 to 105. Using these assumptions, the total 
effective dose equivalent (TEDE) to the maximally exposed individual 
onsite was estimated to be approximately 0.15 mSv/yr (15 mrem/yr), 
which is less than one fifth of the dose limit for members of the 
public specified in 10 CFR 20.1301.
    NRC probably overestimated the dose because it assumed that 
decommissioning of all areas of the facility will be conducted 
simultaneously, that Th-232 and Sr-90 are the predominant radionuclides 
released, and that there is no dilution from the release point to the 
individual exposed. Actual exposures are expected to be far lower. 
There are an estimated 2,000 employees at the GA facility, which 
results in a population dose of 0.3 person-Sv (30 person-rem), if every 
one of these employees received the maximum estimated individual dose. 
Actual population exposures are expected to be far lower. Doses to off-
site members of the public are expected to be orders of magnitude lower 
due to dilution of the radionuclide concentrations.
    An accident analysis was included in a 1995 Environmental 
Assessment, performed by the U.S. Department of Energy, to analyze 
impacts from Decommissioning of GA's Hot Cell Facility. This analysis 
concluded that there was no significant risk from accidents during 
decommissioning of this facility. This analysis is considered bounding 
for the decommissioning activities of the proposed action.
    Cumulative impacts from the proposed action were also considered. 
As noted previously, substantial decommissioning activities have been 
conducted at the site since the mid 1980s. Continuous environmental 
monitoring of the site throughout this period until the present has not 
detected any significant environmental impacts. The only on-going 
activities authorized by the NRC are the decommissioning activities 
discussed in the proposed action and decommissioning of the Hot Cell 
Facility, which has been previously approved. The environmental 
assessment performed for the Hot Cell Facility decommissioning project 
by the U.S. Department of Energy estimated a dose of 
4 x 10-4 mSv/yr (0.04 mrem/yr) to the on-site, member of the 
public (who was considered to be the maximally exposed individual) and 
concluded that there were no environmental impacts. Cumulative impacts 
from decommissioning of the Hot Cell Facility and the operations 
specified in the site DP are, therefore, also expected to be 
insignificant. The TRIGA research reactors are currently not operating. 
The environmental impact from decommissioning of these facilities will 
be considered under the NRC Reactor Licenses.

Alternatives to the Proposed Action

    The alternative to the proposed action is to deny approval of the 
Site DP and either require that the site be maintained in its 
contaminated state under the NRC license or terminate the license after 
completion of partial decommissioning, but impose site or area 
restrictions to protect the public from residual radioactivity.
    This alternative would reduce the quantity of radioactive effluents 
expected during decommissioning of the facilities to levels suitable 
for unrestricted use. However, if contamination is left in-place there 
is a potential for the spread of this material to unaffected areas. 
Decommissioning at a later time may then result in increased effluents. 
If GA is unable to release these areas for unrestricted use, the 
company may also be economically impacted by the inability to sell or 
lease the facilities and by the resources required to maintain the 
site. The public would also not have the opportunity to use these areas 
productively.

Agencies and Persons Consulted

    The DP was approved by the State of California by License Amendment 
dated July 5, 1996. The NRC staff consulted GA and the State of 
California, Department of Health Services, but did not consult any 
other State or Federal agencies in preparation of this Environmental 
Assessment.

Conclusion

    Extensive decommissioning operations have been conducted at the GA 
facility since the mid-1980's. Effluent and environmental monitoring 
data indicate that all off-site radioactive releases have been below 
the effluent and dose limits established in 10 CFR Part 20 and have not 
resulted in any significant human health or environmental impact.
    Future decommissioning operations are expected to be similar to 
decommissioning conducted previously by the facility and are, 
therefore, not expected to result in any significant environmental 
impact. This conclusion is also supported by a conservative dose 
assessment performed by the staff, which estimates a dose to the 
maximally exposed onsite individual of approximately 0.15 mSv/yr (15 
mrem/yr). This is significantly below the dose limit for members of the 
public of 1 mSv/yr (100 mrem/yr) specified in 10 CFR part 20.
    In addition, GA has committed to engineering controls, waste 
handling methods, and an effluent and environmental sampling program to 
keep releases as low as reasonably achievable and to ensure continued 
compliance with applicable laws and regulations.
    Given the engineering controls, waste handling procedures, 
projected doses to members of the public and workers, and demonstrated 
ability to conduct these activities without adverse impacts to the 
environment, the staff concludes that the proposed action can be 
implemented without significant environmental impacts.
    This environmental assessment was conducted based on preliminary 
characterization information. If further characterization data 
indicates that significantly greater concentrations of radionuclides or 
significantly different types of radionuclides may be released off-
site, or if GA determines that significantly different decommissioning 
activities will be required that may result in significant impacts to 
workers or the environment, GA will be required to notify the NRC for 
review and approval of the proposed decommissioning activities.

Finding of No Significant Impact

    The NRC has prepared an Environmental Assessment related to the 
amendment of Special Nuclear Material License SNM-696. On the basis of 
this assessment, NRC has concluded that the proposed licensing action 
would not cause significant environmental impacts and does not

[[Page 20673]]

warrant the preparation of an Environmental Impact Statement. 
Accordingly, it has been determined that a finding of no significant 
impact is appropriate.
    The Environmental Assessment, the license amendment application, 
and other documents related to this proposed action are available for 
public inspection and copying at the Commission's public document room 
in NRC's Region IV office, Harris Tower, 611 Ryan Plaza Drive, Suite 
400, Arlington, Texas 76011-8064, and in NRC's headquarters public 
document room, Gelman Building, 2120 L St., NW., Washington, DC 20037.

Opportunity for a Hearing

    Based on the EA and accompanying safety evaluation, NRC is 
preparing to amend License SNM-696. The NRC hereby provides notice that 
this is a proceeding on an application for amendment of a license 
falling within the scope of Subpart L, ``Informal Hearing Procedure for 
Adjudication in Materials Licensing Proceedings,'' of NRC's rules and 
practice for domestic licensing processing in 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 a hearing in accordance with 
Sec. 2.1205(d). A request for a hearing must be filed within thirty 
(30) days of the date of this publication of the Federal Register 
notice.
    The request for a hearing must be filed with the Office of 
Secretary either:
    1. By delivery to the Docketing and Service Branch of the Secretary 
at One White Flint North, 11555 Rockville Pike, MD 20852-2738; or
    2. By mail or telegram addressed to the Secretary, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555. Attention: Docketing and 
Services Branch.
    In addition to meeting other applicable requirements of 10 CFR part 
2 of 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 requester in the proceeding;
    2. How that interest may be affected by the results of the 
proceeding, including reasons why the requested should be permitted a 
hearing, with particular reference to the factors set out in 
Sec. 2.1205(h);
    3. The requester's areas 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 10 CFR 2.1205(f), each request for a hearing 
must also be served, by delivering it personally or by mail to:
    1. The applicant, General Atomics, 3550 General Atomics Court, San 
Diego, CA 92121-1194; Attention: Dr. Keith E. Asmussen; and
    2. The NRC staff, by delivering to the Executive Director for 
Operations, One White Flint North, 11555 Rockville Pike, Rockville, MD 
20852, or by mail, addressed to the Executive Director for Operations, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555.
    Any hearing that is requested and granted will be held in 
accordance with the NRC's Informal Hearing Procedures for Adjudications 
in Material Licensing Proceedings in 10 CFR part 2, subpart L.
    Questions with respect to this action should be referred to NRC's 
project manager for General Atomics, Charles Gaskin, at (301) 415-8116 
or via Internet at [email protected].

    Dated at Rockville, Md., this 20th day of April 1998.

    For the Nuclear Regulatory Commission.
Michael F. Weber,
Chief Licensing Branch, Division of Fuel Cycle Safety and Safeguards, 
NMSS.
[FR Doc. 98-11123 Filed 4-24-98; 8:45 am]
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