Multi Canister Overpack (MCO) Topical Report [SEC 1 THRU 6]
In February 1995, the US. Department of Energy (DOE) approved the Spent Nuclear Fuel (SNF) Project's ''Path Forward'' recommendation for resolution of the safety and environmental concerns associated with the deteriorating SNF stored in the Hanford Site's K Basins (Hansen 1995). The recommendation included an aggressive series of projects to design, construct, and operate systems and facilities to permit the safe retrieval, packaging, transport, conditioning, and interim storage of the K Basins' SNF. The facilities are the Cold Vacuum Drying Facility (CVDF) in the 100 K Area of the Hanford Site and the Canister Storage Building (CSB) in the 200 East Area. The K Basins' SNF is to be cleaned, repackaged in multi-canister overpacks (MCOs), removed from the K Basins, and transported to the CVDF for drying. The MCOs would then be moved to the CSB and weld sealed (Loscoe 1996) for interim storage (about 40 years). One of the major tasks associated with the initial Path Forward activities is the development and maintenance of the safety documentation. In addition to meeting the construction needs for new structures, the safety documentation for each must be generated. A common thread that was identified among the structures was the MCO. Each structure exists for the specific purpose of treating or storing the MCO and its contents. Normally, an extensive amount of MCO-related documentation would be generated for each of the facility safety analysis reports. However, the expedited schedule for removing spent fuel from the K Basins requires that the documentation effort be minimized and repetitious activities be eliminated. Therefore, this topical report has been prepared to address those aspects of the MCO that will be common to the facilities. The MCO will be included in each facility's safety documentation by reference to this topical report. By capturing the design of the MCO and its safety evaluation in a single document, repetition, inconsistency, and duplication of effort is minimized. As changes are made to the MCO, the MCO Topical Report can be updated to retain the validity of references to the report. By submitting the topical report for early review and approval, it will be possible for the facility safety analysis reports to reference the Topical Report for much of the MCO design information.
- Research Organization:
- Fluor Hanford, Richland, WA (United States)
- Sponsoring Organization:
- USDOE Office of Environmental Management (EM) (US)
- DOE Contract Number:
- AC06-96RL13200
- OSTI ID:
- 808571
- Report Number(s):
- HNF-SD-SNF-SARR-005, Rev.3; ECN-666573; TRN: US0302376
- Resource Relation:
- Other Information: PBD: 21 Jan 2002
- Country of Publication:
- United States
- Language:
- English
Similar Records
Spent Nuclear Fuel [SNF] Project Canister Storage Building [CSB] Final Safety Analysis Report [FSAR] Volume 1 [Section 1-3]
SNF project's MCO compliance assessment with DOE ''general design criteria,'' order 6430.1A and ''SNF project MCO additional NRC requirements,'' HNF-SD-SNF-DB-005