Technical & Regulatory Review of Radioactive Facilities

 

 

Dry Transfer System (DTS) is used to transfer spent nuclear fuel from one type of cask into another.

 

 

 

 

 

 

 

 

For more information, contact:
Asadul H. Chowdhury, Ph.D.
(210) 522-5151
achowdhury@swri.org

Southwest
Research
Institute
Sponsor:  U.S. Nuclear Regulatory Commission
Principal Investigator:  Luis Ibarra Olivas, Ph.D.

Statement of Service: Performed Safety Review of the proposed Dry Transfer System (DTS) facility Topical Safety Analysis Report (TSAR), including independent analyses necessary to ensure regulatory compliance with 10 CFR Part 72.

Approach and Accomplishments: Assisted the U.S. Nuclear Regulatory Commission staff in technical and regulatory reviews of U.S. Department of Energy (DOE) contractor documents, identified technical uncertainties and potential safety issues, and performed independent evaluations of proposed technologies or calculations used by the DOE contractor to support the safety case. This task included review of the (i) generic site design criteria; (ii) design criteria and design bases for the various structures, systems, and components of the DTS, including the external conditions during normal and off-normal operations, accident conditions, and natural phenomena events; (iii) description of all operations, including systems, equipment, and instrumentation, particularly as these relate to handling and transfer of spent nuclear fuel, confinement of nuclear material, and management of expected and potential radiological dose; (iv) descriptions related to development and implementation of operating and maintenance procedures; (v) confinement and management of any radioactive waste generated as a result of facility operations; (vi) installation of design and structural integrities; (vii) thermal calculations used to demonstrate that fuel material temperatures remain within allowable values or criteria for normal, off-normal, and accident conditions; (viii) radiation protection for workers and the general public; (ix) criticality potential for normal, off-normal, and accident conditions; (x) postulated off-normal and accident scenarios and concomitant recovery operations; and (xi) proposed functional and operational limits.

The CNWRA® staff with experience in mechanical engineering, structural engineering, geotechnical engineering, fire technology, health physics, risk analysis, corrosion engineering, chemical engineering, facility design engineering, nuclear criticality, and controls and instrumentation were used to accomplish the task.

Client Benefits: The final Assessment Report (AR) for the DTS TSAR was prepared by the multi-disciplinary team at CNWRA. The AR provided a comprehensive and detailed listing of the information that would have to be provided in the site-specific license application to fully satisfy the requirements of 10 CFR Part 72.

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August 07, 2014