A Graded Approach to Safety Analysis for Rover Processing Facility Deactivation

Conference · Sun Sep 07 00:00:00 EDT 1997

OSTI ID:542026

Henrikson, Deborah J. ^[1]

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1. Lockheed Martin Idaho Technologies Company, Idaho National Engineering and Environmental Laboratory (INEEL), Idaho Falls, ID (United States)

The Rover Fuels Processing Facility operated in the early 1980's, recovering uranium from graphite fuels. In 1996 clean-out began of uranium bearing material remaining in the Rover cells where combustion processes had occurred. Success of the Rover Deactivation Project depends on the safe, timely, and cost-effective repackaging and removal of the uranium bearing material. Due to a number of issues which could not be resolved prior to clean-out, and consideration of cost and schedule objectives, a graded approach was taken to projected design and criticality safety analysis. The safety authorization basis was upgraded primarily by a specific Deactivation addendum, instead of being completely rewritten to current format and content standards. In place of having all design activities completed prior to the start of the Deactivation, the project design and accompanying safety documentation evolved as the project progressed. The Unreviewed Safety Question determination process was used to ensure that new project activities were within the safety envelope. This graded approach allowed operational flexibility while maintaining a critically safe work environment.

• Research Organization: Lockheed Martin Idaho Technologies Company, Idaho National Engineering and Environmental Laboratory (INEEL), Idaho Falls, ID (United States)
• Sponsoring Organization: USDOE National Nuclear Security Administration (NNSA), Nuclear Criticality Safety Program (NCSP); USDOE Assistant Secretary for Environmental Management (EM); USDOE Idaho Operations Office (IO)
• DOE Contract Number: AC07-94ID13223
• OSTI ID: 542026
• Report Number(s): INEL/CON-97-00185; CONF-970952-; ON: DE97053242; TRN: 98:008443
• Resource Relation: Conference: Decontamination, Decommissioning and Reutilization of Commercial and Government Facilities , Knoxville, TN (United States), 7-12 Sep 1997; Other Information: PBD: 1997
• Country of Publication: United States
• Language: English

Related Subjects

11 NUCLEAR FUEL CYCLE AND FUEL MATERIALS
96 KNOWLEDGE MANAGEMENT AND PRESERVATION
IDAHO CHEMICAL PROCESSING PLANT
DECOMMISSIONING
SAFETY ANALYSIS
DECONTAMINATION
CRITICALITY
Nuclear Criticality Safety Program (NCSP)
NESDPS Office of Nuclear Energy Space and Defense Power Systems
Criticality Safety Analysis
Rover Fuels Processing Facility
Uranium Bearing Material (UBM)
Intact Fuel Rod
Uranium Fuels
Graphite Fuels