Initial Review of the
Environmental Impacts of the Portsmouth Gaseous Diffusion Plant
for PRESS and UEP
by Lynn
dela Merced Radioactive Waste
Management Associates
October 2000
Portsmouth Gaseous Diffusion
Plant
A. Operational History
One of the nation’s three uranium-enrichment
facilities, the Portsmouth Gaseous Diffusion Plant (or PORTS) sits on
3,708 acres of land near the Village of Piketon, 20 mi north of
Portsmouth, and about 1 mi east of the Scioto River in Pike County1.
Owned by DOE-until 1993, PORTS was first operated under
contract by Goodyear Atomic from 1956 to 1986, followed by Lockheed
Martin Energy Systems (formerly, Martin Marietta Energy Systems) from
1986 to 1998. On July 1, 1993, control of Portsmouth passed from the DOE
to the United States Enrichment Corporation (USEC), a wholly owned
government corporation created by Congress in an attempt to transform
the DOE’s uranium enrichment enterprise into a profitable business.
The USEC, which also operates another former DOE enrichment facility in
Paducah, KY, was privatized on July 28, 19982. The
current contractor is Bechtel Jacobs.
When it began operations in 1954, the Portsmouth Plant’s
mission has been to enrich uranium (that is, increase the concentration
of U-235) for government and commercial purposes. Only 0.711% U-235 is
found naturally in uranium. Through a process known as gaseous
diffusion, uranium hexafluoride (UF6) is passed through a
series of converters and compressors to yield a product enriched to 97%
U-235 for the nuclear weapons and naval nuclear propulsion programs.
Uranium at 2 to 7% enrichment is removed as a side product for use in
light-water reactors3,4. At present, Portsmouth works in
tandem with Paducah to produce only low-grade, commercial uranium for
use by civilian power and naval reactors5. Paducah performs
the initial phase of separating uranium for reactor fuel and then ships its product to
Portsmouth for a second stage to further raise the concentration of
fissile uranium to 3 to 5%6,7.
DOE, who retains responsibility for environmental
restoration and waste management activities at the site, and USEC have
both acknowledged pollution problems8 but have consistently downplayed
the gravity of the problem.
Plant processes, especially the cleaning and changeout
of process equipment, generated spent solvents and other chemical and
radioactive contaminants that were disposed of in onsite landfills and
surface impoundments. The chemical contaminants include chlorinated
solvents (such as tricholoroethylene or TCE), chlorinated solvents mixed
with radionuclides in low concentrations, polychlorinated biphenyls
(PCB), and metals (such as arsenic, antimony, cadmium, beryllium,
chromium, and lead). Radioactive contaminants found in process
equipment, buildings, cooling towers, burial grounds and wastewater
ponds include uranium, plutonium, neptunium, and technetium9.
Two aquifers beneath the Plant store and supply
groundwater; one is shallow and the other is deep. DOE reports that only
the shallow aquifer is contaminated, with TCE being the main contaminant
of concern and that the shallow aquifer is not of sufficient volume to
be a source of drinking water. DOE maintains that no groundwater
contamination has migrated offsite10. Arguments similar to these were used
at the Pantex plant in Texas, where a shallow "perched"
aquifer, supposedly confined, has now been found to be leaking into the
much larger Ogallala aquifer, despite DOE’s earlier assurances. TCE is
now contaminating the Ogallala Aquifer.
Contamination has also been detected in Little Beaver
Creek and Big Run Creek11. The Little Beaver Creek is the largest natural
body of water on PORTS. During much of the year, particularly summer,
wastewater from the Portsmouth Plant provides almost all of the flow in
the Little Beaver, which empties into the Big Beaver Creek offsite. Big
Beaver Creek enters the Scioto River, which then flows into the Ohio
River12. An April 1992 Ohio EPA study revealed that tissue from fish
collected in area creeks around PORTS had PCBs and elevated levels of
radiation. Stream sediments also showed radiation levels 5 times above
the natural level, as well as increased concentrations of PCBs and heavy
metals such as arsenic, cadmium, chromium, and mercury. At one site on
Little Beaver Creek, the total uranium measured by the EPA was nearly
twice the level at which corrective action would be required at civilian
nuclear plants13. A second survey of the creeks and streams surrounding
the facility is underway. The Ohio EPA expects to complete the study
this year14.
Since the 1950s, the Portsmouth facility has released
more than 40,000 pounds of uranium and an unreported amount of the
radioactive gas, technetium-99, into local creeks and the air15. A 1991
DOE report revealed that uranium-contaminated wastes were routinely
burned at the Plant from the mid-1950s to 1996. These wastes also
contained larger-than-allowable amounts of heavy metals such as mercury,
barium and cadmium. In a 1992 document, the DOE reported the release of
23,122 lb of uranium into the air and 17,123 lb of uranium into the
water from 1955 to 1987. The report also recounted specific instances of
pollution that have occurred at the Plant since its opening. One such
example occurred on July 17, 1975 when the Portsmouth facility released
250,000 gallons of hypochlorate (a sterilizing chemical) from a
decontamination building to a drainage ditch16.
As of 1998, there are 13,388 cylinders of depleted
uranium hexafluoride stored at the Portsmouth site17. Several cylinders
have been found to be leaking. When a cylinder is rusted through, UF6
reacts with air to form compounds of uranium and fluorine. Some of these
compounds are solid and plug the leak. However, the metal continues to
corrode. Both radiation and hydrogen fluoride (a deadly gas even when
diluted by air) can escape18. In March 1978, more than 13,000 lb of
uranium hexafluoride (UF6) escaped when a cylinder was dropped and
ruptured19. The Plant managers’ report about the incident described such
releases of UF6 as routine. They also claimed no one was injured,
contrary to what workers present at the Plant at that time have said20.
Technetium-99 (Tc-99), although not naturally occurring
in uranium ore, has contaminated PORTS because of the re-enrichment or
recycling of uranium from experimental and naval reactors. Strongly
adherent to internal piping and equipment, it builds up on enrichment
converters and compressors. PORTS workers were exposed to technetium
when equipment was opened for repair, upgrading or replacement. When
technetium compounds are allowed to react with moist air, it hydrolyzes
to form pertechnic acid, which also diffuses as a gas. On April 2, 1977,
smoke emissions began in the X-705 (decontamination building) as soon as
seals were removed from a converter taken from the enrichment process
building (X-326). Tremendous amounts of red and orange smoke were seen
escaping through closed overhead doors and cracks in the walls, and
carried into other areas by strong drafts. Areas 200 feet from the
release point became contaminated. Technetium levels were measured and
found to be 5.7 times the allowable levels in the Plant.
Most of the time though, technetium was released as
liquid effluent generated in the process of decontaminating the piping
and equipment, and as solid waste in discarded or buried piping and
equipment. In 1975, X-705 released 83 Ci of Tc-99 to a local stream. A
weekly average sample in the east drainage ditch at PORTS exceeded the
State of Ohio’s radiation limit (100 Ci gross beta per liter) by more
than 300,000 times. PORTS personnel have estimated that peak Tc
concentrations may have exceeded ERDA (now, DOE) standards by a factor
of 20 and the State standard by 6,000,000. After 1975, the Plant tried
to correct the problem by installing an ion exchange facility for X-705
effluents that will remove Tc-99. After removal of technetium, the ion
exchange resins were placed in 55-gallon drums in the outdoor hot yard.
PORTS acknowledged that this "solution" is also problematic,
as it is possible for an exponential exothermic chemical reaction to
occur similar to the chemical explosion of an americium-loaded ion
exchange column at Hanford21. Since Tc-99 (a fission product) has been
found in PORTS pipes and effluents, transuranics such as Pu, and fission
products are likely to be present in the plant environs as well.
The DOE began a massive cleanup of the site in the
1980s. Not satisfied with the progress of the cleanup, the Ohio EPA
entered into a Consent Agreement with the DOE and began monitoring
operations at Portsmouth in 198922. At the same time, DOE entered into a
separate Consent Order with the US EPA. Since the Portsmouth site has
not been included in the Superfund program, remediation efforts are
conducted under the RCRA Corrective Action Program23.
Workers at the Portsmouth facility were never told of
the potential health dangers involved. Plant managers withheld crucial
workplace-safety information from the rank and file24,25. Workers
were given either inadequate or improper protective gear or none at all26,27.
They have testified before Congress that radiation exposure data were
either not collected or were altered28. They have also testified that
monitoring was lax or non-existent. Several Piketon workers are
afflicted with or have died from a host of illnesses, including cancer
and lung diseases. They believe that these diseases and deaths are
related to their exposure to work areas that were contaminated with
chemicals and radionuclides29.
At first, a DOE report released to the Ohio EPA in
August 1999 claimed that all the initial conversion and most of the
initial enrichment was done at Paducah. As a result, the uranium
material sent to Piketon for further enrichment had much lower plutonium
levels and DOE was insisting that worker exposure at Portsmouth was
negligible. DOE officials estimated that only one ounce of plutonium
went to Piketon over the years, compared to the 12 ounces received at
Paducah30.
However, in September 1999, DOE officials confirmed that
Piketon had its own conversion plant and got some of the plutonium-laced
uranium directly. According to DOE documents, the enrichment of uranium
from spent nuclear fuel at Piketon was halted in 1977 for fear that
workers were being exposed to deadly radiation. The part of the X-705
building used to convert the raw reactor material was closed in 1978
because of concerns about leaks of radioactivity. However, other parts
of the building are still being used today by USEC employees31.
Just how much plutonium was processed and what amounts
of exposure occurred at PORTS from the 1950s to the 1970s is still
unclear32. The DOE now admits it doesn’t know how much reactor fuel was
processed at Portsmouth33. It is likely that all the uranium and plutonium
from West Valley reprocessed fuel was sent to Fernald, then onto
Portsmouth. In 1993 and again in 1998, officials released a report
regarding the presence of plutonium in the environment, including Little
Beaver Creek34. Past testing of the nearby patch of ground that received
waste from the X-705 building indicated the presence of significant
levels of plutonium35.
DOE has recently concluded its own two-part
investigation into plant practices at Portsmouth36. They have found
current practices to be significantly weak and inadequate in terms of
radiological characterization (monitoring), radiation protection
capability, and site management and oversight. Historical operations
have put workers and the environment at great risk, with production
schedules and costs taking precedence over health physics concerns and
uranium inventory control.
Meanwhile, USEC has announced that it will cease PORTS
operations in June of next year. However, DOE plans to keep the plant on
standby and conduct research on new enrichment technologies.
Congress has recently approved a bill, which would
compensate nuclear weapons workers, including those from the Paducah and
Piketon plants, with $150,000 and lifetime healthcare benefits.
B. DOE Independent Investigation (May
2000)
Past practices
According to the Independent Investigation, management
at PORTS was inconsistent and ineffective. Environment, safety and
health oversight was not rigorous. The emphasis was on production while
concerns regarding health physics were secondary. Hazards were not
effectively communicated to workers, with some supervisors telling
workers that uranium is safe enough to eat. The belief that uranium was
relatively harmless partly contributed to workers not wearing personnel
protective equipment, such as respirators, even when performing work in
areas with extensive airborne contamination. PORTS’ Health Physics
group noted there was reluctance among Operations supervisors to
implement or enforce their recommendations and follow Plant procedures,
resulting in PORTS’ inability to control personnel exposure to
radioactive materials.
Radiation and contamination surveys were available from
the start of the Plant operations. Contamination exceeding limits were
found in all major buildings over several years. Follow-up surveys
revealed some areas continued to be contaminated above limits. This was
attributed partly to a lax enforcement of decontamination requirements.
One of the most hazardous working conditions for PORTS
workers existed at the X-705E building, where oxide conversion took
place, from 1958 to 1978. Originally designed to recover and convert
oxides of uranium from decontamination solutions in X-705 and
incinerator ash into UF6, it later processed uranium oxides
from spent reactor fuel between 1959 and 1961. In 1965, it was
temporarily shut down due to health physics concerns and uranium
material balance problems. A 1965 Oak Ridge health protection review
revealed potential concentration of transuranics in the processes,
internal uranium exposure from enriched insoluble oxides undetectable by
urinalysis, and inadequate air monitoring capability. The investigation
team found a 1966 handwritten report explaining that the facility was
not designed to handle or process reactor returns. It also mentioned
that the practice of "de-smoking ash pots through the building
ventilation system" likely explained the physical losses of small
quantities of uranium. (The investigation team noted that the building
ventilation system was unfiltered and reactor return materials had been
processed in this facility; therefore, transuranics from the ash pots
also likely entered the building ventilation system and were
subsequently released to the environment unmonitored.)
Process modifications were then made, such as enclosing
the process in a glove box, which were completed in 1967. Operations
resumed in November 1967. However, efforts to reduce health physics
problems between 1967 and 1973 were futile as operators and supervisors
failed to follow operating procedures and protective measures. In 1976,
a PORTS memo identified transuranics as a problem in the Plant,
especially in X-705E. At that time, PORTS had an inventory of
transuranic-contaminated feed materials for oxide conversion, which they
wanted to process. Based on Oak Ridge recommendations, PORTS made some
process improvements and performed test runs to model fluorination of
transuranics and reduce leaks and contamination. In September 1978, the
Health Physics management concluded these efforts were not enough, that
the health risks were unacceptable, and recommended that X-705E be shut
down. In October 1978, the oxide conversion facility was put on standby.
Finally, in December 1978, PORTS requested cancellation of the oxide
conversion project. Samples obtained after the shutdown showed
transuranics at levels that indicated worker airborne exposures could
have exceeded acceptable standards.
X-344, the feed manufacturing plant, converted uranium
tetrafluoride (UF4), a.k.a. "green salt", to UF6
by reacting green salt with fluorine at high temperatures. Personnel
recounted that the work environment was harsh, with exposure to uranium
dust commonplace, room temperatures in tower areas exceeding 100F, and
noise levels high. Hoppers, conveyers, and towers frequently broke down
or clogged up. Green salt inside broken equipment were cleaned by hand
by operators and maintenance personnel continuously worked on
contaminated equipment. Powder spills were common and personnel
recounted that green salt accumulated to several inches deep in some
areas each shift. Ash, which resulted from the fluorination of UF4
and found in piles in the tower pits, were reported to emit up to 6 rad/hr
of beta-gamma radiation on contact, with 700 mrad/hr coming from gamma
radiation. Operators were exposed to these radiation levels when they
cleared out ash plugs in the towers and when they changed ash receivers.
The investigation team found health physics surveys of X-344 routinely
showing high levels of alpha contamination, even after decontamination.
During normal operations, a 1961 survey indicated that radiation levels
1 foot from the fluorination towers were usually 50 mrad/hr or less.
During one six-month period, the maximum level measured was 100 mrad/hr.
It is estimated that about 12,000 metric tons of UF4 was
processed in X-244, with more than 400 kg of uranium lost each year to
the atmosphere in the form of dust and fumes. Workers wore overalls and
gloves, while respirator use was inconsistent.
At PORTS, equipment was decontaminated and uranium was
recovered from decontamination solutions at X-705, the Decontamination
building. Physically separate from the oxide conversion area, the
hazards associated with the decontamination and recovery areas included
radionuclides (such as Tc, U, and transuranics), acids, organic solvents
(such as TCE), asbestos, and PCBs. The health physics personnel
discovered that hands, shoes, and coveralls were frequently contaminated
with radioactive materials. Limits for airborne radioactive materials
were often exceeded in X-705. Radiological hazards in X-705 were
considered significant because they handled equipment that were involved
in uranium recovery and oxide conversion processes, which tended to
concentrate transuranic materials, fission products, and insoluble forms
of uranium. Prior to the mid-1970s, it was assumed that all
radioactivity detected in X-705 was due to uranium only.
Workers were also exposed to various toxic gases,
solvents, and metals at PORTS. TCE was widely used as a degreaser and
general cleaning agent. Mercury was used in several process equipment
and chemical traps. Beryllium exposure may have resulted from machining
of Be Cu-alloy piping components, use of Be as a coating on light bulbs,
and use of welding rods that contained Be.
The public may also have been exposed to PORTS
contamination through the contaminated scrap and surplus materials that
were auctioned off or sold to the public. This likelihood stemmed from
the investigation team’s review of reports documenting PORTS’
failure to consistently segregate clean and contaminated materials and
perform pre-sale surveys of the items.
Incidents of routine or accidental or planned releases
of radioactive materials and fluorine were frequent. However, onsite and
offsite air monitoring was not initiated until the mid-1960s. It is
estimated that more than 23,000 lb of uranium and 27 Ci of technetium
were released into the atmosphere from 1954 to 1993. The biggest release
was in March 1978, when a cylinder of UF6 was dropped and
ruptured, releasing over 13,000 lb UF6 to the environment.
Other major releases of uranium that occurred involved valve failures on
tails cylinders and process malfunctions in purge cascades. As for
fluorine and/or fluorides, one significant release occurred in July
1973, when a 30- to 40- foot high column of hydrogen fluoride vapor was
observed coming out the X-342 vent stack. At other times, there were
several reports of offensive fluorine fumes, breathing difficulty, and
in some cases respiratory tract damage attributed to fluorine releases.
Vent emissions were not monitored continuously until the
mid-1980s. Although grab sampling was performed and space recorders were
used to monitor vent emissions, they proved to be problematic,
unreliable and inaccurate, prompting a Vent Committee formed in the
1980s to recommend continuous monitoring.
"Jetting", that is purging the cascade cells
of uranium to prepare it for maintenance or repair, were routinely done
and unmonitored throughout Plant history.
Diffuse and fugitive emissions were not monitored but
can be confirmed with notable contamination found on roofs, grounds, and
work areas. One example would be the practice of de-smoking ash pots
through X-705E building’s unfiltered ventilation system, which
resulted in the release of unknown quantities of uranium and
transuranics to the environment.
Releases of liquid effluents from Plant operations to
the environment were also typical. These effluents were discharged via
sanitary sewer and storm water drainage systems. Effluent materials that
did not go through wastewater treatment facilities and recovery systems
were routed to the various outfalls and ditches that led to Little
Beaver Creek and ultimately to the Scioto River. Little Beaver Creek,
which flows into Big Beaver Creek (which flows into the Scioto River),
received most of the Plant effluents, mainly from the north and east
sides of the Plant.
The X-701B holding pond was a major effluent source to
Little Beaver Creek. Unlined, most of the waste discharged to the pond
came from the X-705 Decontamination Building and X-700 Chemical Cleaning
Facility.
The X-700 facility used TCE from 1955 to 1987 for
degreasing. It was the major source of TCE in X-701B and the entire east
drainage ditch area.
Most X-705 process effluents were discharged to the
X-701B holding pond. Uranium comprised 92% (76.5 kg) of the total
radioactivity released to the holding pond in 1969 and 90% (117 kg) of
the total in 1970. PORTS was not monitoring the liquid effluents for
transuranics and technetium around that time. However, by 1976,
transuranics had been identified in X-705 raffinates, which were
discharged to the X-701B holding pond. Subsequent monitoring revealed
high levels of transuranics in the sludge of the holding pond and in the
effluents from the pond to the east drainage ditch. In 1977, PORTS
investigated transuranic contamination in Little and Big Beaver Creeks’
sediments. Some samples had low levels of plutonium and neptunium.
The investigation team found 1977 interdepartmental
documents, which revealed that effluents from the X-705 cleaning
facilities were bypassing X-701B and discharging directly to the east
drainage ditch, which led to the Little Beaver Creek. This was
reportedly corrected shortly after discovery.
Over the years, fish kills occurred in Little Beaver and
Big Run Creeks reportedly due to oxygen depletion or elevated
concentrations of metals or sodium hydroxide spills, which resulted from
spills at and discharges from the Plant.
Current practices
Although DOE found current environmental and health
risks have been reduced, practices at the Plant still leave much to be
desired. PORTS has not adequately characterized and analyzed the
contamination problem.
Significant weaknesses were discovered in the Plant’s
radiation monitoring program, which puts into question exposure and risk
estimates, and cleanup decisions and progress. They have designed and
conducted radiological surveys that do not meet DOE standards. They have
eliminated various media from surveillance. For example, direct sediment
sampling at liquid discharge points is not being performed. Some surface
water outfalls are not being evaluated. Their radiological sampling has
been limited to generic analyses (such as gross alpha, gross beta, total
uranium), instead of testing for specific isotopes, making it impossible
then to establish compliance with isotope-specific standards and
requirements, and resulting in an underestimate of radiological risks.
For example, data on gross alpha measurements in water were incorrectly
compared to a DCG of 600 pCi/L for gross alpha activity in water. DCGs
are derived dose-based numbers and thus defined only for individual
isotopes. A DCG of 600 pCi/L is defined for U-238. A DCG of 500 pCi/L is
specified for U-234. As DOE has said, there is no method for comparing
gross alpha measurements against isotopic limits. PORTS’ monitoring
program has NEVER showed any detectable transuranic contamination in any
of their samples. However, an OH EPA investigation found low levels of
plutonium in Little Beaver Creek sediments and DOE’s independent
investigation found detectable levels of transuranics in most stream
sediment samples on the east side of the plant and from X-6619 outfall
(wastewater treatment plant).
Radiological exposure pathways have not been fully
assessed since not all effluent emission/discharge points are being
monitored and evaluated. In air, for example, fugitive emissions from
PORTS are still not completely known. The DOE investigation team found
that some air samplers have been out of service for more than 6 months.
Air strippers at groundwater treatment facilities are not being checked
for Tc-99, and no health physics surveys of air are being conducted in
these areas.
Radiological risks have been underestimated. Since PORTS
has little or no isotopic uranium data needed for risk assessments, they
calculated the isotopic uranium composition from total uranium mass by
wrongly assuming natural uranium isotopic ratios. Transuranics were not
included in risk assessments since PORTS never detected them, while
certain uranium daughter products were inexplicably not factored into
risk estimates.
Remediation progress is in doubt. For example, it is
claimed that TCE and Tc-99 contamination of groundwater has not migrated
offsite due to PORTS’ efforts, such as the installation of a slurry
wall at the X-749 landfill that is supposed to intercept these
contaminants. However, this assertion cannot be confirmed because PORTS
is not sampling beyond the slurry wall to verify its effectiveness in
intercepting the contamination.
Independent investigation team’s sampling results
In general, sampling results obtained by investigation
team are consistent with past environmental sampling results taken by
PORTS. Analyses of samples taken by the investigation team and split
with PORTS are in broad agreement, except when it came to transuranics.
DOE concluded that the discrepancies arose from less sensitive
equipment used by PORTS in its analysis.
Groundwater sampling has confirmed that it is
contaminated with radionuclides, metals, and VOCs. Uranium, thorium,
neptunium, and technetium were all detected. Uranium, thorium and
neptunium were well below DCGs. In one well, X705-01G, Tc-99 was
detected at 5,439 pCi/L, a level that would exceed EPA drinking water
standards of 4 mrem/yr. TCE is the VOC of major concern, with levels
significantly exceeding the 5-mg/L MCL, up
to 4,800 times at the X-230J7 interceptor trench. Concentrations of
aluminum and iron exceeded secondary drinking water standards.
Beryllium was not detected while chromium was found at very low levels
in some samples.
Uranium, thorium, neptunium, and technetium were
detected in surface water, although at levels not exceeding DCGs. A
sample taken from the outfall of the sewage treatment facility had
Np-237 of 0.29 pCi/L. Although well below the DCG, the fact that
neptunium was detected is in direct contrast with PORTS’ not
detecting any transuranics so far. Plus, this sample came from liquid
that was already processed and filtered at the sewage treatment
facility, so the input concentration must have been much higher.
Uranium levels were low; however, if one takes the uranium
mass-to-activity ratios for the collected samples, they indicate
enrichments higher than that of natural uranium, up to 4%.
Concentrations of aluminum, iron, and manganese that exceeded
secondary public drinking water standards were detected in surface
water samples. Chromium and beryllium were not detected.
Uranium, Th-230, Tc-99 were detected in all sediment
samples, which were taken from area streams and Little Beaver Creek.
Contamination was found to be above background. The uranium
mass-to-activity ratio for one sample indicates a more than 10% U-235
enrichment, much higher than what is ‘normal’ for natural uranium.
Low concentrations of transuranics were found in several sediment
samples that were taken from Little Beaver Creek and the streams that
discharge into it. The concentration of Pu-238 ranged from 0.001 to
0.008 pCi/g while Pu-239/240 ranged from 0.002 to 0.037 pCi/g. Np-237
ranged from 0.004 to 0.054 pCi/g. PCBs were detected in all samples
and concentration ranged from 35.8 to 644 mg/kg.
C. Conclusion
Historically, it was found that uranium inventory control and
health physics concerns were secondary to production schedules and
costs. Radioactive and hazardous materials were spilled or routinely
released to the environment from production-related facilities and
work activities. Environmental releases and worker exposures were
grossly underestimated due to poor monitoring. Safety and health
programs were not adequately implemented and were ineffective in
protecting the workers.
Radiation monitoring data taken by PORTS are deficient. Risk
analysis and cleanup goals and actions, which were based on inadequate
data, are thus questionable. Any conclusions reached regarding PORTS
operations and remediation must be re-examined.
Under the RESOLVE grant, RWMA will be working with PRESS and UEP to
conduct an independent review of data, studies, and reports on PORTS.
With DOE’s permission, a site tour will be conducted to familiarize
us with the lay of the land. We will look into the presence of
transuranics (such as plutonium) and fission products (such as Tc-99).
In particular, we will be reviewing the monitoring data in the East
Drainage Ditch, X-705E landfills, X-701B holding pond, X-700 facility
and Little Beaver Creek for the presence of Tc-99 and transuranics.
RWMA will also investigate the environmental and health effects (both
on- and off-site) of PORTS operations. We will also evaluate the
progress and effectiveness of the site cleanup, and make
recommendations to the PRESS and UEP and to State and Federal
agencies.
1
MB Lafferty. "US burned radioactive waste at Piketon plant", The
Columbus Dispatch, 11/21/93.
2
SI Schwartz. US Nuclear Weapons Research, Development, Testing, and
Production, and Naval Nuclear Propulsion Facilities, 10/12/99.
3
Department of Energy (DOE). Environmental Assessment, Construction
and Operation of an Industrial Solid Waste Landfill at Portsmouth
Gaseous Diffusion Plant, Piketon, Ohio, DOE/EA-0767, Oct 1995.
4
M Resnikoff. Cost/Benefits of U/Pu Recycle, 10/11/82.
5
J Riskind. "Senate to Investigate Past Safety Practices Piketon
Nuclear Plant", The Columbus Dispatch, 3/3/00.
6
J Malone. "Plant’s reaction risk to be studied", The
Courier-Journal, 3/2/00.
7
USEC has recently announced its intentions to upgrade the Paducah plant
so that it can enrich uranium independently of Portsmouth. They are
considering laying off workers and shutting down one facility to cut
costs. (J Walker. "USEC upgrade sought in Paducah", Paducah
Sun, 3/3/00; J Riskind, "USEC privatization debate fueled by
‘power politics’", The Columbus Dispatch, 4/12/00).
8
Lafferty, 11/21/93.
8
Department of Energy (DOE). 1996 Baseline Environmental Management
Report, 1996.
10
Ibid.
11
"The state’s Big 3 messes", The Columbus Dispatch,
10/1/95.
12
DOE, 1995.
13
MB Lafferty. "Radiation high in fish near Piketon", The
Columbus Dispatch, 2/7/93.
14
Ohio Environmental Protection Agency. Portsmouth Gaseous Diffusion
Plant, 3/22/00, http://offo2.epa.state.oh.us/PORTSMOUTH/portsmouth.htm.
15
"The state’s Big 3 messes", The Columbus Dispatch,
10/1/95.
16
Lafferty, 11/21/93.
17
D Daniels. "DOE hears input on draft statement", Portsmouth
Daily Times, 2/27/98.
18
M Lafferty. "Huge tanks of nuclear waste rusting away", The
Columbus Dispatch, 3/10/96.
19
DOE. Independent Investigation of the Portsmouth Gaseous Diffusion
Plant, vol. 1, May 2000.
20
J Riskind. "Piketon’s heavy toll", The Columbus Dispatch,
10/29/99.
21
Resnikoff, 1982.
22
Lafferty, 2/7/93.
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