Waste acceptance criteria

Leaching Tests, Recommending Agency, Test Function, and Significance. 

Toxicity characteristic leaching procedure (TCLP) us EPA [13] Measures the solubility of hazardous constituents. Used to determine if a waste is hazardous and to pass/fail the waste form for disposal 

Product consistency test (PCT) DOE [14] Measures dissolution of structural elements of the waste form. Determines durability of radioactive waste forms in hot aqueous environment during storage 

ANS 16.1 American Nuclear Society [15] Measures bulk dififiisivity of waste constituents. Evaluates long-term leaching of radioactive contaminants from low-level waste forms 

MCC-1 American Society for Testing and Materials [16] Evaluates long-term leaching rate of radioactive contaminants from high- and low-level radioactive waste forms 

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Process pH, sodium, calcium, and nitrate concentrations, plugging of the ion exchange column, lot variance, and the presence of binders can affect process efficiency. lonsiv IE-911 does not remove anionic radioactive ions such as technetium. The resins are designed for one-time use and must be replaced when loaded. The waste acceptance criteria at the resin disposal facility may limit the loading of the CST resin. Size constraints of the cesium removal system (CRS) may limit system flow rates. 

In many cases, the mechanical properties of a waste form are an important part of the waste acceptance criteria for storage and/or disposal of the waste. The waste form may undergo a series of tests, such as a determination of its compressive strength, to demonstrate that it will maintain its integrity over the required period of time. 

Classification system applies to any waste that contains radionuclides or hazardous chemicals. Waste classification system does not provide a substitute for site-specific risk assessments in developing waste acceptance criteria at particular disposal facilities or in developing criteria for remediation of particular contaminated sites. 

As emphasized in Section 1.1, the recommended approach to classifying waste does not provide a basis for establishing waste acceptance criteria at specific disposal sites. NCRP expects, however, that waste classified as exempt or low-hazard in accordance with its recommendations should be acceptable for disposal in the associated type of disposal facility at well-chosen sites. 

A risk-based waste classification system must focus on the inherent characteristics of waste, representative facilities, and generic events, because the system necessarily presumes that specific disposal sites and related waste treatment and disposal technologies have not yet been identified and characterized. NCRP emphasizes that the principles, framework, and implementation details of a risk-based waste classification system do not provide a substitute for site-specific risk assessments. The two most important cases where site-specific risk must be estimated are (1) an assessment of risk for the spectrum of actual wastes at a specific disposal site for the purpose of establishing site-specific waste acceptance criteria, and (2) an assessment of risk posed by a prior waste disposal at a site for the purpose of determining whether the risk is unacceptable and, thus, whether remedial action is required at the site. 

In most cases, evaluations of ecological impacts are site-specific and, as a consequence, are not considered when establishing a generally applicable waste classification system. These impacts normally are addressed in disposal site selection, design, and operation, and they may be used in establishing waste acceptance criteria for the site. To the extent that ecological impacts can be evaluated generi-cally, NCRP believes that the principles and framework for risk-based waste classification presented in this Report are sufficiently flexible to take them into account. 

The dominance of the risk to inadvertent intruders at near-surface waste disposal sites allows the use of this type of scenario to develop a risk-based waste classification system. However, NCRP recognizes that exposures of the public and protection of the environment also are of concern in determining acceptable disposal practices at specific sites. The potential for off-site releases of hazardous substances is the primary reason that classification of waste based on risks to hypothetical inadvertent intruders does not obviate the need for site-specific risk assessments to determine waste acceptance criteria in the form of limits on disposal of particular hazardous substances. 

Substantial amounts of mixed low-level waste continue to be stored and inventories are increasing. Little of this waste is being sent to facilities intended for permanent disposal because few exist and those that are operating have restrictive waste acceptance criteria. 

NCRP reiterates that the risk-based waste classification system developed in this Report does not, and cannot, obviate the need to establish waste acceptance criteria at each hazardous waste disposal site based on the characteristics of the site, the particular disposal technology, and characteristics of the wastes that are intended for disposal at the site. NCRP expects that most waste that would be assigned to a particular class will be acceptable for disposal using the associated type of disposal technology indicated in Figure 6.1. However, the disposal capabilities of particular sites and engineered systems can vary substantially and can depend on the waste characteristics. The primary function of any waste classification system is to facilitate development of cost-effective approaches to waste management and disposal and effective communication on waste matters (see Section 2.1.2). 

In addition, the reliance on generic scenarios for inadvertent intrusion in classifying waste cannot, by definition, represent site-specific risks. However, this is not a serious shortcoming because such scenarios have been used in establishing subclasses of low-level radioactive waste for disposal in near-surface facilities (NRC, 1982a). Furthermore, as emphasized in this Report, establishment of a risk-based waste classification system using particular exposure scenarios does not obviate the need to perform site-specific risk assessments for the purpose of establishing waste acceptance criteria at each disposal site. 

Facilities located at a considerable depth below the ground surface, such as mined cavities, are used in some countries (e.g., Germany) for disposal of hazardous chemical wastes, as well as low-level radioactive waste. However, the selection of a deep disposal system often is based on general land-use policies that prohibit disposal of hazardous wastes on or near the land surface, as well as a desire to protect public health and the environment, and no distinction is made between wastes that pose a lesser or greater hazard in selecting such disposal systems and in developing site-specific waste acceptance criteria. 

Another credible assumption is that permanent access to the site could occur at the end of the 100 y period of institutional control. This assumption has been used in establishing waste acceptance criteria at all DOE low-level waste disposal sites (DOE, 1988c 1999c), including the Hanford site, based on an acceptable dose from chronic exposure of an inadvertent intruder of 1 mSv y Therefore, the waste acceptance criteria for the Hanford site already take into account an acceptable dose to an inadvertent intruder from permanent site occupancy, so the waste is acceptable for near-surface disposal as low-hazard waste according to this scenario without the need for further analysis. 

Development of a comprehensive and risk-based hazardous waste classification system, in which waste classes are defined in relation to types of disposal systems that are expected to be generally acceptable in protecting public health, would not obviate the need to establish waste acceptance criteria at each disposal site based on the characteristics of the site and engineered disposal facility and the properties of wastes intended for disposal therein. The primary purposes of a hazardous waste classification system are to facilitate cost-effective management and disposal of waste and effective communication on waste matters. 

DOE (1996a). U.S. Department of Energy. Waste Acceptance Criteria for the Waste Isolation Pilot Plant, DOE/WIPP-069, Rev. 5 (Waste Isolation Pilot Plant Project Office, Carlsbad, New Mexico). 

All the NPPs have their own systems for managing the solid and liquid radioactive waste generated at the site. The very low level waste (VLLW) and the low and intermediate level short lived radioactive waste (L IL SL) waste is eonditioned in accordance with the waste acceptance criteria for the landfill type and the SFR repository respectively. Standard techniques are used processing liquid and solid waste. Cement and bitumen are used as matrix for conditioning. 

For the disposal of L IL SL generated at the Swedish NPPs a repository has been established in crystalline rock (as required by the Swedish strategy) 50 m under the seabed outside Forsmark NPP. Following an agreement with the Government and the authorities the repository is also used for radioactive waste from Swedish use of radionuclides in medicine, research and industry that meets the waste acceptance criteria approved by the authorities for the repository. 

Based on the half-life and specific activity of commonly occurring isotopes in radioactive waste streams given in Table 17.2, each disposal site or repository of the treated waste has developed waste acceptance criteria (WAC). The WACs require that the treated waste pass certain test criteria, which vary from site to site depending on the nature of the waste stored. In a number of case studies discussed in this chapter, we will use these WACs to demonstrate compliance of the CBPC waste form. 

Compliance tests that are used to determine whether the material complies with specific reference values such as soil screening levels for remediation purposes, or waste acceptance criteria for landfill disposal. These tests focus on key variables and aspects of leaching behaviour identified by basic characterisation tests. 

Table 1 provides a listing of the current Saltstone waste acceptance criteria (WAC) for 90Sr and selected alpha-emitting radionuclides. These limits establish the target concentrations that the process used in the SWPF for 90Sr and actinide removal must meet. 90Sr removal performance originally served as the chief criterion for selection of MST for use in radiochemical separations at the SRS. With increased characterization of SRS wastes, actinide removal performance has increased in importance. 

Table 1, Saltstone Waste Acceptance Criteria for Selected Radionuclides...

Groups within the ES H Center are responsible for all off site waste shipments. Regulatory requirements for packaging and off site shipment are outlined in the SNL ES H Manual (SNL 1998b). The ES H Center Is responsible for ensuring that offsite waste shipments meet all applicable Department of Transportation requirements, RCRA manifesting requirements, and the waste acceptance criteria of the receiving treatment and/or disposal facility. 

In addition to the requirements imposed by the repository licensing activities, the WIPP facility safety analysis established requirements for worker safety that have been incorporated into the repository waste acceptance criteria (WAC). The licensing phase of the WIPP repository program involved the most stakeholder participation, especially from the federal and sfafe regulatory agencies, fhe public-at-large, and the State of New Mexico local communify. These interactions defined conditions for WIPP operations. 

Performance Based Waste Acceptance Criteria Pirlinunary Baseiloe Assumptions 10/94... 

The safety relevant characteristics of the waste packages which are allowed to be disposed of at the facility must be derived from the results of performance assessments. These safety relevant characteristics form the waste acceptance criteria. 

Performance assessments to derive waste acceptance criteria should be based on site specific data which have to be gathered by site investigations. They should be done for the operational phase of the disposal facility and for the long-term post closure phase. Normal operation or evolution and unexpected but possible accidental situations must be covered. 

In due course, hfirex wiE issue waste acceptance criteria and all waste packages will have to comply with these before being accepted for disposal The acceptance criteria will be determined principally by the safety standards to be achieved, including requirements specified in the authorisation for disposal, but will also take account of design constramts, legal, operational and economic factors... 

Waste acceptance criteria shall be established for radionuclide content consistent with assumptions made in the repository design. 

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