Protocol for development of authorized release limits for concrete at U.S. Department of Energy sites

Arnish, J.; Kamboj, S.; Chen, S.-Y.; Parker, F.L.; Smith, Agatha Marie; Meservey, R.H.; Tripp, Julia

doi:10.2172/764202

Cited by 2 publications

(7 citation statements)

References 6 publications

Supporting

Mentioning

Contrasting

Order By: Relevance

“…Specifically, it defines the contamination levels allowed for each isotope that equate to doses of less than 1 millirem (mrem) per year to the maximally exposed individual (MEI). Authorized limits may be derived and approved by DOE Field Office managers without EH-1 approval if certain conditions are met (Arnish et al, 2000) 6 . One of the conditions is that the release of the concrete material will not cause a maximum individual dose to a member of public in excess of 1 mrem in a year or a collective dose of more than 10 person-rem in a year.…”

Section: Existing Release Standards and Regulationsmentioning

confidence: 99%

“…If the release will not cause an MEI dose to a member of the public in excess of 1 mrem/yr or a collective dose of more than 10 person-rem/yr, records of the release are made per DOE Order 5400.5, DOE survey guidelines are maintained, and required documentation (as outlined in Section 2.5 of the protocol 6 ) is submitted to EH-1 within the required time frames, the DOE field office can approve release of volumetrically contaminated material.…”

Section: Doe Approvals Requiredmentioning

confidence: 99%

See 1 more Smart Citation

Cost and Performance Report for the ASTD Reuse of Concrete Within DOE from D&D Projects

Kamboj¹,

Arnish²,

Chen³

et al. 2000

View full text Add to dashboard Cite

This cost and performance report describes the Accelerated Site Technology Deployment project that developed the Protocol for Development of Authorized Release Limits for Concrete at U.S. DOE Sites, which identifies the steps for obtaining approval to reuse concrete from Deactivation and Decommissioning of facilities. This protocol compares the risk and cost of various disposition paths for the concrete and follows the authorized release approach described in the DOE's draft handbook, Controlling Release for Reuse or Recycle of Property Containing Residual Radioactive Material. This approach provides for the development of authorized release limits through a series of prescribed steps before approval for release is granted. A case study was also completed on a previously decommissioned facility.iii iv SUMMARYThe purpose of the Reuse of Concrete within DOE from D&D project was to develop a protocol that will assist DOE sites in releasing concrete for reuse. Current regulations allow for release of surface-contaminated materials that fall below certain radioactivity levels and the possible release of volumetrically contaminated materials or higher levels of surface-contaminated materials on a case by case basis. In all cases, an ALARA analysis is required as part of the release process. This protocol, titled the Protocol for Development of Authorized Release Limits for Concrete at U.S. Department of Energy Sites, provides a standardized approach, including an ALARA analysis, for evaluating the risks of releasing volumetrically contaminated or higher levels of surface-contaminated concrete, so new release standards can be proposed and set, allowing reuse of the concrete material.The protocol provides a method to perform a detailed analysis of the dose and cost impact for various disposition alternatives. Once the dose and cost impact of the various alternatives has been estimated, the protocol outlines the steps required to propose new release standards that allow release and reuse of the concrete material.In order to evaluate the dose impacts of reusing radioactively contaminated material, the measured radiation levels (pCi/g or DPM/100 cm 2 ) must be converted to estimated dose (mrem/yr) received by affected individuals. The dose depends on the amounts and types of isotopes present and the time, distance, and method of exposure (e.g., inhalation, ingestion, or exterior exposure). For each disposition alternative, the protocol provides a systematic method to evaluate the dose impact on the affected individuals. Likewise, the cost impacts of reusing the concrete are dependent on the disposition alternative chosen and on the extent and type of contamination. This paper summarizes the project and its accomplishments, beginning with a description of the need for a concrete protocol. It then details the project objective, outlines team roles, discusses existing standards for release of concrete, and summarizes the concrete protocol. It concludes with a summary and analysis of the case study, a description of th...

show abstract

Section: Existing Release Standards and Regulationsmentioning

confidence: 99%

Section: Doe Approvals Requiredmentioning

confidence: 99%

Cost and Performance Report for the ASTD Reuse of Concrete Within DOE from D&D Projects

Kamboj¹,

Arnish²,

Chen³

et al. 2000

View full text Add to dashboard Cite

show abstract

“…Two case studies (one generic and one INEEL-specific) were used to illustrate the use of the concrete release protocol (Arnish et al 2000) to develop authorized release limits and select disposition alternative(s) that minimize radiological doses to members of the public while also minimizing costs associated with D&D activities for the CFA STP.…”

Section: Authorized Release Processmentioning

confidence: 99%

“…Radiological dose analysis unit dose factors from Arnish et al (2000) were used with the characterization data to calculate the radiological impacts for the different disposal alternatives. It was assumed that even after decontamination, concrete would still be contaminated at 1/10 of the initial contamination level (Table 2).…”

Section: Radiological Dose Analysismentioning

confidence: 99%

“…To clarify and implement DOE's release provisions, protocols are being developed to assist in obtaining authorization to release the concrete material for unrestricted use. The protocol used for the case studies reported here (Arnish et al 2000) contains 10 steps to reach an appropriate decision on disposition alternatives. The purpose of this analysis was to use the 10-step process for concrete structures (digester, trickle filter and primary tank, secondary tank and 691 pumphouse, deep well at CFA-691, 657 pumphouse at the CFA STP) to support an appropriate disposition alternative.…”

Section: Introductionmentioning

confidence: 99%

See 1 more Smart Citation

Concrete release protocol case studies for decommissioning work at the Idaho National Engineering and Environmental Laboratory

Kamboj¹,

Arnish²,

Sy³

et al. 2000

Self Cite

View full text Add to dashboard Cite

U.S. Department of Energy (DOE) Order 5400.5, "Radiation Protection of the Public and Environment" contains provisions pertinent to releasing potentially radioactive materials from DOE facilities for reuse or recycle. A process of "authorized" release for materials recovered from radiation areas is permitted under Order 5400.5 and the proposed rule in Title 10, Part 834, of the Code of Federal Regulations (10 CFR Part 834). 1 A generic disposition protocol to facilitate release of concrete under these provisions has been developed. This report analyzes the application of that generic protocol to site-specific cases at the

show abstract

Protocol for development of authorized release limits for concrete at U.S. Department of Energy sites

Cited by 2 publications

References 6 publications

Cost and Performance Report for the ASTD Reuse of Concrete Within DOE from D&D Projects

Cost and Performance Report for the ASTD Reuse of Concrete Within DOE from D&D Projects

Concrete release protocol case studies for decommissioning work at the Idaho National Engineering and Environmental Laboratory

Contact Info

Product

Resources

About