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

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