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7x)qiim/o 0 13+- &417-6 jL The Design of a Phase I Non Site-Specific
Centralized Interim Storage Facility
October 28,1997
Written by: Joe Strihger, Design Manager, CISF Design Group
Dan Kane, Department of Energy
DISCLAIMER
This report was prepared as an account of work sponsored by an agency of the United States Government. Neither the United States Government nor any agency thereof, nor any of their employees, makes any warranty, express or hplied, or assumes any legal liability or responsibility for the accuracy, completeness, or use- fulness of any information, apparatus, product, or process disclosed, or represents that its usc would not infringe privately owned rights. Reference herein to any spe- cific commercial product, process, or service by trade name, trademark, manufac- turer, or otherwise does not necessarily constitute or imply its endorsement, recom- mendation, or favoring by the United States Government or any agency thereof. The views and opinions of authors expressed herein do not necessarily state or reflect those of the United States Government or any agency thereof.
The Design of a Phase I Non Site-Specific Centralized Interim Storage Facility (CISF)
Introduction
The Department of Energy (DOE), Office of Civilian Radioactive Waste Management
(OCRWM) recently completed a Topical Safety Analysis Report (TSAR) for a Phase I non
site-specific Centralized Interim Storage Facility (CISF). The TSAR will be used in licensing the
CISF when and if a site is designated. The combined Phase I and Phase I1 CISF will provide
federal storage capability for 40,000 metric tons of uranium (MTU) Spent Nuclear Fuel (SNF)
under the oversight of the DOE. The Phase I TSAR was submitted to the NRC on May 1, 1997
and is currently under review having been docketed on June 10, 1997, Docket No. 72-21, This
paper generally describes the Phase I CISF design and its operations as presented in the CISF
TSAR (Reference 1).
General Description of Installation
The CISF site requires approximately 1,200 acres. The CISF is designed to be located almost
anywhere in the United States. The principal design criteria for the CISF are based on generic
site characteristics, the design criteria associated with the vendor systems, and specific discipline
criteria required for facility design. The principle design criteria satisfy the applicable
requirements of 10 CFR 72, Subpart F (Reference 2). The format and content of the CISF TSAR
are in accordance with the Draft NUREG- 1567 Standard Review Plan for Spent Fuel Dry
Storage Facilities (Reference 3).
A preliminary hazards assessment (PHA) was completed which identifies potential radiological
hazards to facility workers, the public and the environment, ranging from normal operation
events through design-basis accidents (DBEs). The PHA ensures that all DBEs considered in the
facility design or analyzed for potential important-to-safety consequences are identified.
Off-normal events or accidents are based on the four levels of design events described in
American National Standards Institute/American Nuclear Society (ANSIlANS) 57.9 (Reference
4).
CISF Functions
The main function of the CISF is to provide safe temporary storage of spent nuclear fuel (SNF).
The CISF will receive, handle, and store SNF in a manner that protects the health and safety of
the public and workers, and maintains the quality of the environment in accordance with 10 CFR
Part 72. Only SNF in NRC-approved dual-purpose cask systems will be received at the Phase I
CISF during the first two years of operations. This will include commercial light water reactor
fuel, pressurized water reactor (PWR) and boiling water reactor (BWR), and possibly
non-commercial fuel. The Phase I facility is designed to receive SNF at the rate of 1200, 1200,
2000,2000, and 2700 MTU per year for the first five years of operation respectively. The design
receipt rate from the sixth year forward is 3000 MTU per year.
The storage of SNF at the Phase I CISF will be based on the use of transportable storage casks
(TSCs) and canister-based storage systems that have been certified by the NRC. For the
preparation of the Phase I CISF design, the following cask systems were utilized.
- VECTRA NUHOMSB System
- Holtec HI-STAR 100 System
- Sierra TranStorTM System
- Westinghouse Large/Small MPC System
- NAC STC System
Facilities Descriptions
The major facilities at the Phase I CISF are the transfer facility and the storage area. The transfer
facility is a reinforced concrete building approximately 250 ft long by 88 ft wide by 75 ft high
(refer to attached transfer facility plan). The purpose of the transfer facility is to receive and
prepare for storage shipments of SNF in dual purpose caskkanister systems. It will also retrieve
SNF from storage and prepare the systems for off-site shipment. The transfer facility is designed
to handle canistered fuel only and does not have any routine bare fuel handling capabilities.
ALARA principles are incorporated to the maximum extent practical throughout the transfer
facility design to reduce radiation exposure to facility personnel. Overhead bridges cranes are
remotely operated from a crane operating room. Gantry-mounted automated equipment is
provided in the shippingh-eceiving area and stationary-mounted automated equipment is provided
in the canister transfer area. The automated equipment is controlled remotely from shielded
rooms.
The storage area is a large area comprised of concrete storage pads and storage casks. The
storage area will be constructed in stages as necessary. Cask transporters are available to
transport storage and transportation casks between the transfer facility and the storage area.
The remainder of the CISF facilities provide support functions such as fuel receipt, fuel
inspection, power, security, water utilities, and fire protection.
Waste Products
Because the Phase I CISF only receives, transfers and stores SNF in NRC-approved sealed
canisters or casks, the quantities of radioactive materials expected to be released as CISF
effluents are very small. Potential sources of liquid radioactive wastes may result from
decontamination of transportation casks in the transfer facility. Low volumes of solid radioactive
wastes are expected from routine operations involving contamination surveillance activities and
decontamination activities. Potential liquid and solid waste streams are collected and
temporarily stored on site for processing and disposal by an off-site contractor. Gaseous wastes
are not generated at the CISF; however, airborne radioactive contamination can be generated in
the transfer facility in the form of aerosols of surface contamination from cask transfer
operations.
Summary
The Phase I CISF design, as described in the CISF TSAR, provides an efficient design for receipt
of commercial SNF contained in canisters or TSCs.
References
1.
2.
Centralized Interim Storage Facility Topical Safety Analysis Report, U.S. Department of
Energy Office of Civilian Radioactive Waste Management, Docket No. 72-21, Rev. 0,
May 1, 1997
10 CFR Part 72. Licensing Requirements for the Independent Storage of Spent Nuclear
Fuel and High-Level Radioactive Waste.
NUREG-1567. Draft Standard Review Plan fo r Spent Fuel Dry Storage Facilities. U.S.
NRC. October 1996.
ANSIIANS 57.9- 1992. Design Criteria fo r an Independent Spent Fuel Storage
Installation (Dry Type). American National Standards Institute and American Nuclear
Society. May 1992.
3.
4.
Publ. Date (1 1) 1-99 7 l O d Sponsor Code (18) a 0 6 CJ JF d C Category (1 9)
DOE
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