Maximally Exposed Individual Research Articles

Site-Specific Reference Person Parameters and Derived Concentration Standards for the Savannah River Site

The U.S. Department of Energy Order 458.1 states that the compliance with the 1 mSv annual dose constraint to a member of the public may be demonstrated by calculating dose to the maximally exposed individual (MEI) or to a representative person. Historically, the MEI concept was used for dose compliance at the Savannah River Site (SRS) using adult dose coefficients and adult male usage parameters. For future compliance, SRS plans to use the representative person concept for dose estimates to members of the public. The representative person dose will be based on the reference person dose coefficients from the U.S. DOE Derived Concentration Technical Standard and on usage parameters specific to SRS for the reference and typical person. Usage parameters and dose coefficients were determined for inhalation, ingestion and external exposure pathways. The reference intake for air, water, meat, dairy, freshwater fish, saltwater invertebrates, produce (fruits and vegetables), and grains for the 95th percentile are 17.4 m d, 2.19 L d, 220.6 g d, 674 cm d, 66.4 g d, 23.0 g d, 633.4 g d (448.5 g dand 631.7 g d) and 251.3 g d, respectively. For the 50th percentile: 13.4 m d, 0.809 L d, 86.4 g d, 187 cm d, 8.97 g d, 3.04 g d, 169.5 g d (45.9 g d and 145.6 g d), 101.3 g d, respectively. These parameters for the representative person were used to calculate and tabulate SRS-specific derived concentration standards (DCSs) for the pathways not included in DOE-STD-1196-2011.

Evaluation and Measurements of Radioactive Air Emission and Off-Site Doses at SLAC

SLAC, a high-energy (GeV) electron accelerator facility, performs experimental and theoretical research using high-energy electron and/or positron beams that can produce secondary neutron and gamma radiation when beam losses occur. Radioactive gas production (mainly C, N, O, Ar) and release is one of the environmental protection program issues. U.S. DOE Order 458.1 requires that 40 CFR 61 Subpart H's NESHAP requirements be followed. These regulations prescribe a total dose limit of 0.1 mSv y to the Maximally Exposed Individual (MEI) of the general public, a requirement for a continuous air monitoring system if a release point within a facility can cause > 1 × 10 mSv y to the MEI, and a requirement for periodic confirmatory measurements for minor sources which give releases that contribute ≤ 1 × 10 mSv y to the MEI. At SLAC, all air release points for current operations are evaluated to be minor sources. This paper describes SLAC's evaluation following NESHAP requirements; measurements using the Air Monitoring Station (AMS) as periodic confirmatory measurements are also discussed.

Carcinogenic risk assessment for emissions from clinical waste incineration and road traffic

The most significant potentially carcinogenic substances arising from a state-of-the-art clinical waste incinerator (CWI) and vehicle emissions were identified as polychlorinated dibenzo-p-dioxins, polycyclic aromatic hydrocarbons (PAHs), benzene, 1-butadiene, arsenic, cadmium, chromium and nickel. Long-term exposures of the notional maximum exposed individual (MEI) in the local environment, together with aggregate emissions from transport of clinical waste, were estimated. Mass emission rates of PAHs from the CWI to air were compared with previously published estimates of mass emissions to land from CWI bottom ash. Aggregate emissions from road transport of clinical waste were of a similar order to stack emissions from incineration. Mass emissions of PAHs to landfill generally greatly exceeded those from stack emissions. Emissions associated with operation of the CWI present a negligible contribution to overall cancer risk from PAHs and other carcinogens. Uncertainty in the quantitative risk estimates presented here is discussed in the context of these findings.

Critical Radionuclide/Critical Pathway Analysis for the U.S. Department of Energy's Savannah River Site

Many different radionuclides have been released to the environment from the Savannah River Site (SRS) during the facility's operational history. However, as shown by this analysis, only a small number of the released radionuclides have been significant contributors to potential doses and risks to off-site people. This article documents the radiological critical contaminant/critical pathway analysis performed for SRS. If site missions and operations remain constant over the next 30 years, only tritium oxide releases are projected to exceed a maximally exposed individual (MEI) risk of 1.0E-06 for either the airborne or liquid pathways. The critical exposure pathways associated with site airborne releases are inhalation and vegetation consumption, whereas the critical exposure pathways associated with liquid releases are drinking water and fish consumption. For the SRS-specific, nontypical exposure pathways (i.e., recreational fishing and deer and hog hunting), cesium-137 is the critical radionuclide.

Critical radionuclide/critical pathway analysis for the U.S. Department of Energy's Savannah River Site.

Many different radionuclides have been released to the environment from the Savannah River Site (SRS) during the facility's operational history. However, as shown by this analysis, only a small number of the released radionuclides have been significant contributors to potential doses and risks to off-site people. This article documents the radiological critical contaminant/critical pathway analysis performed for SRS. If site missions and operations remain constant over the next 30 years, only tritium oxide releases are projected to exceed a maximally exposed individual (MEI) risk of 1.0E-06 for either the airborne or liquid pathways. The critical exposure pathways associated with site airborne releases are inhalation and vegetation consumption, whereas the critical exposure pathways associated with liquid releases are drinking water and fish consumption. For the SRS-specific, nontypical exposure pathways (i.e., recreational fishing and deer and hog hunting), cesium-137 is the critical radionuclide.

On the assessment of the maximally exposed individual (MEI) at superfund sites using Monte Carlo simulations

In this paper, the methodology used by the United States Environmental Protection Agency (EPA) to protect a small population that may be at high risk, referred to as the “maximally exposed individual”; (MEI) is assessed. Monte Carlo techniques and more reasonable values for exposure parameters are used to determine a more physiologically reasonable MEI. The Monte Carlo MEI is compared to the EPA's quantification of the MEI as well as the results of a standard MC assessment. In general, the EPA's estimate of MEI risks were found to be much larger (one to three orders of magnitude) than the Monte Carlo MEI risk estimates, showing that using default maximum values results in overestimated risks. In comparing the risk distributions of the Monte Carlo MEI with the Monte Carlo nominal population, one can conclude that the existence of a MEI in the nominal population is highly unlikely. However, by regulating at a higher percentile risk value of the nominal population, a small percentage of the MEI population may be protected. Nonetheless, it is important to consider the MEI in the decision‐making process.

Human Exposure Assessment II: Quantifying and Reducing the Uncertainties

Alternative methods of human exposure assessment that reduce and/or allow quantification of the uncertainties associated with exposure estimates are surveyed and illustrated. These alternative approaches include (1) use of more appropriate exposure parameter default values rather than values that result in extreme exposure estimates; (2) incorporation of time-activity data to better define appropriate exposure duration values; (3) the use of reasonable exposure scenarios rather than the traditional Maximally Exposed Individual (MEI) approach; (4) the use of stochastic approaches such as Monte Carlo-based and information analysis-based methods; (5) use of bivariate analysis to identify the extent to which interdependencies between different exposure parameters affect the distribution of exposure estimates; (6) use of less-than-lifetime exposure and risk assessment; and (7) incorporation of physiological considerations relevant to absorbed dose estimation, including route-specific impacts, use of improved absorption factors, and application of pharmacokinetic models. Other ways to improve the exposure assessment process, including assuring statistical equivalency in comparing different exposure estimates and incorporation of sensitive subpopulation considerations are also discussed, as are key research needs.

Envrionmental and Safety Aspects of “OSIRIS”: A Heavy Ion Beam Driven IFE Reactor

AbstractA detailed safety analysis was performed for the inertial confinement fusion reactor OSIRIS. The radioactivity induced in the carbon fabric chamber concrete shield and Flibe breeder is very low allowing for their disposal at the end of the reactor life as Class A low level waste (LLW). The biological dose rate after shutdown behind the reactor biological shield shield is very low (0.11 µmrem/hr) allowing only for hands-on maintenance. A total of 91.5 Ci/day are routinely released to the environment producing an off-site dose to the maximally exposed individual (MEI) of 2.43 mrem/yr at the reactor site boundary. Only a small fraction (0.2%) of the reactor first wall would be mobilized during a loss of coolant/loss of flow accident. The decay heat generated in the concrete shield is very low such that its temperature would only increase by less than 2 degrees during such an accident OSIRIS contains 660 tonnes of liquid Flibe as a coolant and breeder. A severe accident including a breach of the react...

Conservatism in maximally exposed individual (MEI) predictive exposure assessments: A first-cut analysis

The United States Environmental Protection Agency (USEPA) sometimes applies exposure assessment models based upon the concept of a hypothetical “maximally exposed individual” (MEI) as a means of dealing with uncertainty. This concept has been described in the benzene NESHAPS rule, the proposed RCRA Corrective Action Rule, and the Clean Air Act reauthorization debate. This paper describes a first-cut analysis of the level of conservatism of the current MEI approach relative to a central estimate of exposure of the most exposed population around a source. The inherent level of conservatism of the current MEI model, which appears to be at least one order of magnitude, is usually left unstated. The significance of this conservatism is described along with some proposals for future research.

Assessment of the human health risks posed by exposure to chromium‐contaminated soils

Millions of tons of chromite-ore processing residue have been used as fill in various locations in northern New Jersey and elsewhere in the United States. The primary toxicants in the residue are trivalent chromium [Cr(III)] and hexavalent chromium [Cr(VI)]. The hazard posed by Cr(III) is negligible due to its low acute and chronic toxicity. In contrast, Cr(VI) is a human carcinogen following inhalation of high concentrations. It can also cause allergic contact dermatitis. This evaluation addresses a residential site where the arithmetic mean (x) and geometric mean (gm) concentrations of Cr(III) in soil were 2879 and 1212 mg/kg (ppm). The mean and geometric mean concentrations of Cr(VI) were 180 and 4 mg/kg, respectively. The uptake (absorbed dose) of Cr(III) via soil ingestion, consumption of homegrown vegetables, and ingestion of inspired particles was determined. The uptake of Cr(VI) via dermal absorption from contact with surface soil and building wall surfaces, as well as inhalation, was also evaluated. The techniques used in this assessment are applicable for evaluating the human health risks posed by any residential site having contaminated soil. The potential for both sensitized and unsensitized persons to develop allergic contact dermatitis due to exposure to soil contaminated at these levels was found to be negligible. The estimated average daily dose (ADD) via ingestion and dermal absorption for the maximally exposed individual (MEI) was about 1500- and 40-fold below the EPA reference dose (RfD) for Cr(III) and Cr(VI), respectively. It was shown that for residential sites, the most important route of exposure to Cr(III) was incidental soil ingestion. Although not relevant to these sites specifically, if garden vegetables could be successfully grown in these soils, then they would probably be the predominant source of uptake of Cr(III). Since inhalation of Cr(VI)-contaminated dust (but not ingestion or dermal contact) poses a cancer hazard, the doses and associated risks were assessed. The estimated cancer risks for the MEI and most likely exposed individual (MLEI) were approximately 5 x 10(-9) and 2 x 10(-9), respectively. These levels of risk have always been considered well below those that warrant regulatory concern. For persons living on residential properties, the cancer risk due to inhaling suspended particles is likely to be less than 1 in 1,000,000 if Cr(VI) levels in soil are less than 180 mg/kg (ppm). Based on this analysis, the levels of Cr(III) and Cr(VI) at this and similar sites do not pose a health hazard following acute or chronic exposure.