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Occupational radiation dose assessment for a non site specific spent fuel storage facility

Description: To expedite the licensing process of the non site specific Centralized Interim Storage Facility (CISF) the Department of Energy has completed a phase I CISF Topical Safety Analysis Report (TSAR). The TSAR will be used in licensing the phase I CISF if a site is designated. An occupational radiation does assessment of the facility operations is performed as part of the phase I CISF design. The first phase of the CISF has the capability to receive, transfer, and store SNF in dual-purpose cask/canister systems (DPC`s). Currently there are five vendor technologies under consideration. The preliminary dose assessment is based on estimated occupational exposures using traditional power plant ISFSI and transport cask handling processes. The second step in the process is to recommend ALARA techniques to reduce potential exposures. A final dose assessment is completed implementing the ALARA techniques and a review is performed to ensure that the design is in compliance with regulatory criteria. The dose assessment and ALARA evaluation are determined using the following input information: Dose estimates from vendor SAR`s; ISFSI experience with similar systems; Traditional methods of operations; Expected CISF cask receipt rates; and feasible ALARA techniques. 5 refs., 1 tab.
Date: December 1, 1997
Creator: Hadley, J. & Eble, R. G., Jr.
Partner: UNT Libraries Government Documents Department

Radiation analysis for a generic centralized interim storage facility

Description: This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF). The purpose of the analysis is to establish the CISF Protected Area and Restricted Area boundaries by modeling a representative SNF storage array, calculating the radiation dose at selected locations outside the storage area, and comparing the results with regulatory radiation dose limits. The particular challenge for this analysis is to adequately model a large (6000 cask) storage array with a reasonable amount of analysis time and effort. Previous analyses of SNF storage systems for Independent Spent Fuel Storage Installations at nuclear plant sites (for example in References 5.1 and 5.2) had only considered small arrays of storage casks. For such analyses, the dose contribution from each storage cask can be modeled individually. Since the large number of casks in the CISF storage array make such an approach unrealistic, a simplified model is required.
Date: December 31, 1997
Creator: Gillespie, S. G.; Lopez, P. & Eble, R. G.
Partner: UNT Libraries Government Documents Department

Radiation analysis for a generic centralized interim storage facility

Description: This paper documents the radiation analysis performed for the storage area of a generic Centralized Interim Storage Facility (CISF) for commercial spent nuclear fuel (SNF) to establish the CISF Protected Area, Unrestricted Area, and Restricted Area boundaries. In order to model a large (6000 cask) storage array with a reasonable amount of analysis time and effort, a simplified calculational model was developed for the CISF. The CISF is designed to accommodate several different types of SNF storage systems. In order to simplify the calculation of dose rates from the storage area, the Westinghouse Large PWR Multi-Purpose Canister (MPC) is selected as a representative storage system, since sufficient information is contained in its Safety Analysis Report to allow accurate modeling, and the surface dose rates on the MPC are consistent with other storage systems.
Date: July 1, 1997
Creator: Gillespie, S. G.; Lopez, P. & Eble, R. G.
Partner: UNT Libraries Government Documents Department