[Federal Register Volume 59, Number 13 (Thursday, January 20, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-1324]
[[Page Unknown]]
[Federal Register: January 20, 1994]
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NUCLEAR REGULATORY COMMISSION
[License SNM-960; Docket 70-754]
Finding of No Significant Impact and Notice of Opportunity for a
Hearing; Renewal of Special Nuclear Materials; General Electric Co.,
Vallecitos Nuclear Center, Pleasanton, California
The U.S. Nuclear Regulatory Commission is considering the renewal
of Special Nuclear Materials License SNM-960 for General Electric
Company, Vallecitos Nuclear Center (VNC), Pleasanton, California for a
period of 10 years.
Summary of the Environmental Assessment
Identification of the Proposed Action
The proposed action is the renewal of VNC's operating license for
a period of 10 years authorizing the receipt, possession, use, and
transfer of special nuclear material and associated byproduct material.
Authorized activities include assembly, modification, cleaning, and
repair of unirradiated, encapsulated experimental assemblies; chemical,
metallurgical, health physics, and hot laboratory operations; research
and development; and waste treatment.
The Need for The Proposed Action
Operations at VNC primarily support GE Nuclear Fuels Programs
through fuel specimen examination and evaluation. The demand for these
operations will continue as long as GE-designed and fabricated fuels
continue to be used in commercial nuclear power reactors. Renewal of
the license allows continued research into nuclear technologies and
materials which may hold the promise of more efficient and less
polluting energy producing facilities. The products of continued
research may produce positive effects in the years to come, not only
through expanding knowledge and refining technologies applicable to
energy generation, but also by providing alternatives to technologies
that contribute to acid rain.
Environmental Impacts of the Proposed Action
Liquid waste streams are managed to preclude radioactive
contamination under normal operating conditions. Monitoring is
conducted on the industrial wastewater stream (non-contact cooling
water) to confirm the absence of significant levels of radioactivity.
Both VNC's operating procedures and the facility's NPDES Permit require
confirmatory sampling prior to any release from the retention basins.
Prior to the discharge of this stream, grab samples are collected and
analyzed for gross alpha and gross beta-gamma radioactivity to verify
that radioactivity concentrations do not exceed limits specified by
appendix B of 10 CFR part 20. All discharge samples for the week are
accumulated as a weekly composite and analyzed for \131\I. Monthly
basin composites are analyzed for gross alpha and gross beta-gamma
concentrations, and quarterly composites are analyzed for tritium,
\137\Cs, and \60\Co. The effectiveness of effluent controls is
illustrated by the fact that the measured radioactivity concentrations
of liquid releases from VNC do not exhibit a statistically significant
difference when compared to influent samples from the San Francisco
water supply system.
In addition to the industrial wastewater stream at the retention
basins, monitoring is also conducted on the sanitary wastewater stream.
Grab samples are collected and analyzed for gross alpha and gross beta-
gamma radioactivity to verify that radioactivity concentrations do not
exceed limits specified by Appendix B of 10 CFR part 20.
Potentially contaminated liquids are routed to VNC's Radioactive
Liquid Waste Evaporator Plant for processing. Post-processing
condensate from the evaporator is sampled and analyzed for
radioactivity. If levels of radioactivity are less than the values
specified in appendix B of 10 CFR part 20, the condensate is vaporized
and emitted as steam through a continuously sampled stack.
Operations with potential to generate airborne radioactive
contaminants are conducted within a confined, ventilated structure with
exhausts routed to a filtered and monitored stack. The number of stacks
actually monitored or sampled in a given year will vary dependent upon
usage of the facilities. Annual average emission levels as measured by
the airborne radioactive effluent monitoring program indicate that
levels are significantly less than values specified in appendix B of 10
CFR part 20.
VNC has maintained an environmental surveillance program since 1956
in order to determine the impact, if any, of site operations on
radiation levels in the environment surrounding the facility, and
verify the effectiveness of its radiation control and release point
monitoring programs. The program includes routine collection and
analysis of water, vegetation, soil, stream bottom, and air samples
from strategic onsite and offsite locations.
In order to assess whether recent VNC operations may have caused
cumulative impacts on the surrounding environment, recent surveillance
data for the period 1986 through 1990 was reviewed. During this time,
radioactive concentrations in the environment have remained well below
background statistical levels and action levels.
Nonradiological effluents from current GE VNC operations include
airborne emissions from building exhaust stacks, a gasoline pump, a
spent photochemical storage tank and a solvent cleaning facility; and
liquid discharges include industrial wastewater and sanitary
wastewater, as well as clean water discharges. Emissions from stacks
are not monitored for nonradiological pollutants. GE VNC is exempt from
continuous emissions monitoring under Regulation 1, Section 520 of the
Rules and Regulations of the Bay Area Air Quality Management District.
Industrial wastewater releases from GE VNC are monitored in accordance
with the California Regional Water Quality Control Board Order 90-0058
and NPDES Permit. Prior to discharge, water is sampled from each basin
and tested for acceptable pH and radioactivity levels. Aliquots from
all basin discharges are composited and analyzed for chlorides,
chromium, lead, mercury, zinc, nickel, silver, and total dissolved
solids. In addition, at specific intervals, grab sampling is performed
for dissolved copper, dissolved oxygen, turbidity, oil and grease, fish
toxicity, and temperature. All sanitary wastes are routed to an Imhoff
tank; and, after undergoing sand filtration, chlorination, and pH
adjustments, are land disposed on site by irrigation. The NPDES permit
requires no analysis for sanitary waste sprinkled onsite and
establishes no requirements for sampling or analysis. VNC does,
however, sample and analyze for pH, radioactivity, and coliform
bacteria.
During routine operations at VNC, small quantities of radioactive
material are released to the environment. Release levels, however, have
historically resulted in only a small fraction of the offsite
concentration limits specified by regulation. The offsite radiological
impacts associated with airborne emissions during a typical recent year
of normal operations at VNC were assessed by calculation of the
committed effective dose equivalents to the nearest site boundary, and
to the nearest resident, who represents the maximally exposed
individual from VNC operations. Impacts were additionally assessed by
calculation of the collective dose to the population residing within an
80-km (50-mile) radius of the site.
The dose delivered to a hypothetical individual, situated about 360
meters distance from the site boundary, is estimated at one millirem
per year. The highest organ dose is estimated at 1.2 millirem to the
gonads. The nearest actual resident to VNC is considered the maximally
exposed individual, and is situated 450 meters south-southeast of Stack
102A. The annual effective dose to this resident is about 0.8 millirem
from airborne effluents. The highest organ dose is about 0.9 millirem
delivered to the gonads.
To assess the dose delivered to individuals as a result of airborne
emissions from VNC operations, annual average emissions data for the
year 1990 and representative meteorological data were input to the
computer, Code AIRDOS-PC35. The code applies a Gaussian plume
dispersion model to calculate downwind ambient concentrations in air,
and surface depositions. Various pathways for the possible uptake of
radionuclides by an individual, and the effects of irradiation by plume
immersion and ground deposition are then analyzed to estimate the dose
delivered to an individual as a result of the annual release. During
normal operations at VNC, no realistic pathway exists for the offsite
discharge of radioactive materials in liquid effluents. Monitoring of
the liquid pathway has shown that no measurable or significant
concentrations of radioactivity are being discharged. For these
reasons, the offsite impact of radioactive materials discharged via
liquid effluent pathways is considered to be negligible.
Conclusion
Operational and administrative controls at VNC are designed to
ensure that radioactive materials are stored and utilized in such a
manner as to minimize radiation exposures to workers and the
surrounding population. During routine operations at VNC, small
quantities of radioactive material are released to the environment.
Release levels, however, have historically resulted in only a small
fraction of the offsite concentration limits specified by regulation.
Exposure to airborne emissions is assumed to be the only
significant radiological effluent pathway. This pathway was assessed
for impacts to an individual at the site boundary, at the nearest
residence, and to the population within an 80-km radius. The highest
dose at a site boundary location was calculated based on current stack
emissions data. The resulting dose is less than 1 millirem effective,
with the highest organ dose being about 1.2 millirem to the gonads.
From environmental perimeter TLD measurements, a conservative estimate
of gamma-ray dose is 9 millirem for the northern boundary. Both methods
show that doses from facility operations are well within the standards
of 40 CFR part 190, and indicate that VNC will readily comply with the
new requirements of 10 CFR 20.1301.
No significant nonradiological impacts are expected with the
continued operation of the GE VNC. The proposed action would result in
continuation of the current baseline conditions, with no change to the
socioeconomic character of the community. Land currently grazed and
cultivated would continue to be used in the same manner as it has been
in the past. Traffic on area roads, along with its inherent emissions
and noise, would continue as it has in the past. Water use would
continue, with peaks reaching only 4.5 l/s, and with a peak discharge
of only 2.2 l/s. The nonradioactive gaseous emissions from the GE VNC
facilities are relatively minor and will result in only slight
increases of regulated pollutants, and are not expected to contribute
to further deterioration of local air quality.
Alternatives to the Proposed Action
The alternative of no license renewal would end light-water reactor
fuel research and development activities at VNC, particularly the
examination of irradiated fuels, and would remove from service unique
research facilities. Accordingly, GE would be required to seek other
hot cell facilities capable of and willing to do the work (e.g., a
facility not connected with a competitor), to build new facilities
(necessitating proliferation of sites and commitment of new resources),
or abandon reactor fuel improvement research programs altogether.
Another alternative would be to consider licensing with
restrictions in order to mitigate any unacceptable adverse
environmental impacts.
Agencies and Persons Consulted
The following outside agencies were contacted for supporting
documentation:
Alameda County Flood Control and Water Conservation District
Alameda County Planning Department
Bay Area Air Quality Management District
Cal-EPA Department of Toxic Substances Control
City of Livermore Planning Department
Office of the California State Demographer
U.S. Bureau of the Census
Finding of No Significant Impact
The Commission has prepared an Environmental Assessment related to
the renewal of Special Nuclear Materials License SNM-960. On the basis
of the assessment, the Commission has concluded that environmental
impacts that would be created by the proposed licensing action would
not be significant and would not 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 and the above documents related to
this proposed action are available for public inspection and copying at
the Commission's Public Document Room at the Gelman Building, 2120 L
Street NW., Washington, DC.
Opportunity for a Hearing
Any person whose interest may be affected by the issuance of this
renewal may file a request for a hearing. Any request for a hearing
must be filed with the Office of the Secretary, U.S. Nuclear Regulatory
Commission, Washington, DC 20555, within 30 days of the publication of
this notice in the Federal Register; be served on the NRC staff
(Executive Director for Operations, One White Flint North, 11555
Rockville Pike, Rockville, MD 20852); on the licensee (General Electric
Company, Vallecitos Nuclear Center, P.O. Box 460, Vallecitos Road,
Pleasanton, California 94566), and must comply with the requirements
for requesting a hearing set forth in the Commission's regulation, 10
CFR part 2, subpart L, ``Informal Hearing Procedures for Adjudications
in Materials Licensing Proceedings.''
These requirements, which the requestor must address in detail,
are:
1. The interest of the requestor in the proceeding;
2. How that interest may be affected by the results of the
proceeding, including the reasons why the requestor should be permitted
a hearing;
3. The requestor's areas of concern about the licensing activity
that is the subject matter of the proceeding; and
4. The circumstances establishing that the request for hearing is
timely, that is, filed within 30 days of the date of this notice.
In addressing how the requestor's interest may be affected by the
proceeding, the request should describe the nature of the requestor's
right under the Atomic Energy Act of 1954, as amended, to be made a
party to the proceeding; the nature and extent of the requestor's
property, financial, or other (i.e., health, safety) interest in the
proceeding; and the possible effect of any order that may be entered in
the proceeding upon the requestor's interest.
Dated at Rockville, Maryland, this 12th day of January 1994.
For the Nuclear Regulatory Commission.
Robert C. Pierson,
Chief, Licensing Branch, Division of Fuel Cycle Safety and Safeguards,
NMSS.
[FR Doc. 94-1324 Filed 1-19-94; 8:45 am]
BILLING CODE 7590-01-P
