Safeguards Lessons Learned from the Rokkasho Reprocessing Plant - 19502
- Orano Federal Services (United States)
- Japan Nuclear Fuel Ltd. - JNFL (Japan)
Once operational, the Rokkasho Reprocessing Plant (RRP) will have an operating throughput of 800 MT of uranium in irradiated LWR fuel per year. In order to establish effective and efficient safeguards at RRP, the safeguards discussion with the IAEA was initiated in 1988. However, at that time there were no available models or guidelines that could be used as a reference and multiple difficulties were recognized for the implementation of safeguards into a large scale reprocessing plant. Therefore, from 1988 to 1992, a multinational forum, referred to as LASCAR (Large Scale Reprocessing Plant Safeguards) [1], provided the recommendations on how an effective safeguards approach could be implemented into a large scale reprocessing plant while efficiently using existing resources. During the course of safeguards discussions between the IAEA, the State, and JNFL, the use of operator's equipment and measurement systems (by signal splitting with authentication) for inspections was studied. JNFL also examined incorporating inspection requirements into the process design: to reduce the costs associated with system installation and future system maintenance and to ensure effective, efficient, and credible safeguards implementation into the RRP (this approach has essentially become the 'Safeguards by Design (SBD)' process). From these studies and JNFL's experience of implementing safeguards into a new plant [2], JNFL established and applied signal splitting from operator's equipment as a means for providing inspectors required safeguards information. In addition, the LASCAR findings were utilized to establish the safeguards implemented into the RRP. Safeguards implementation into RRP commenced March 31, 2006. On June 4, 2008, the IAEA approved the 'integrated safeguards approach' for RRP. This paper provides a high level overview of the major safeguards implemented at RRP and the lessons learned from this implementation that can be applied to existing or future similar facilities. (authors)
- Research Organization:
- WM Symposia, Inc., PO Box 27646, 85285-7646 Tempe, AZ (United States)
- OSTI ID:
- 23005375
- Report Number(s):
- INIS-US-21-WM-19502; TRN: US21V1302045709
- Resource Relation:
- Conference: WM2019: 45. Annual Waste Management Conference, Phoenix, AZ (United States), 3-7 Mar 2019; Other Information: Country of input: France; 3 refs.; available online at: https://www.xcdsystem.com/wmsym/2019/index.html
- Country of Publication:
- United States
- Language:
- English
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Related Subjects
98 NUCLEAR DISARMAMENT
SAFEGUARDS AND PHYSICAL PROTECTION
DESIGN
IAEA
IDENTIFICATION SYSTEMS
IMPLEMENTATION
IRRADIATION
MAINTENANCE
NUCLEAR FUELS
ON-SITE INSPECTION
RECOMMENDATIONS
REPROCESSING
ROKKASHO REPROCESSING PLANT
SAFEGUARDS
SIGNALS
URANIUM