Concrete release protocol case studies for decommissioning work at the Idaho National Engineering and Environmental Laboratory
The US 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). 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 Idaho National Engineering and Environmental Laboratory (INEEL). The potential radiological doses and costs for several concrete disposition alternatives for the sewage treatment plant (STP) at the Central Facilities Area (CFA) of INEEL were evaluated in this analysis. Five disposition alternatives were analyzed for the concrete: (A) decontaminate, crush, and reuse; (B) crush and reuse without decontamination; (C) decontaminate, demolish, and dispose of at a nonradiological landfill; (D) demolish and dispose of at a nonradiological landfill without decontamination; and (E) demolish and dispose of at a low-level radioactive waste (LLW) facility. The analysis was performed for disposition of concrete from four INEEL structures: (1) trickle filter, (2) primary clarifier, (3) secondary clarifier, and (4) CFA-691 pumphouse for a generic case (based on default parameters from the disposition protocol) and an INEEL-specific case (based on INEEL-specific parameters). The results of the analysis indicated that Alternatives B and D would incur the lowest cost and result in a dose less than 1 mrem/yr (except for the trickle filter, the dose for which was estimated at 1.9 mrem/yr) for nonradiological workers. The analysis indicated that the main contributor to the radiological dose would be cobalt-60 contamination in the concrete. A characterization conducted in 1996 was used in the analysis; therefore, because of radioactive decay, the resultant doses to receptors (now or later) would be less than the values reported in this analysis. For the generic case study, costs associated with Alternatives A and C were shown to be much smaller than for Alternative E. For the INEEL-specific case, in general, costs were much higher for Alternatives A and C than for Alternative E because of on-site disposal with zero disposal cost.
- Research Organization:
- Argonne National Lab., IL (US)
- Sponsoring Organization:
- US Department of Energy (US)
- DOE Contract Number:
- W-31109-ENG-38
- OSTI ID:
- 764203
- Report Number(s):
- ANL/EAD/TM-94; TRN: US0004926
- Resource Relation:
- Other Information: PBD: 22 Sep 2000
- Country of Publication:
- United States
- Language:
- English
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