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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