Draft Environmental Impact Statement (EIS) for Savannah River Site (SRS) Spent Nuclear Fuel (SNF) Management, Savannah River Site, South Carolina

DEPARTMENT OF ENERGY

Draft Environmental Impact Statement (EIS) for Savannah River

Site (SRS) Spent Nuclear Fuel (SNF) Management, Savannah River Site,

South Carolina

AGENCY: Department of Energy.

ACTION: Notice of availability and public meetings.

-----------------------------------------------------------------------

SUMMARY: The Department of Energy announces the availability of the

Savannah River Site Spent Nuclear Fuel Management Draft Environmental

Impact Statement (DOE/EIS-0279D). This draft EIS evaluates the

potential impacts of reasonable alternatives for the safe and efficient

management of spent nuclear fuel and targets stored and scheduled to be

received at the Savannah River Site (SRS), including placing these

materials in a form suitable for disposition.

DATES: The public comment period began on December 24, 1998 and extends

through February 8, 1999. DOE will consider comments postmarked or

submitted after February 8, 1999 to the extent practicable. Oral and

written comments will be accepted at public meetings on the dates and

at the locations given below. The Department will hold two public

meetings, with two sessions each, to discuss the Draft EIS and receive

comments:

1. Thursday, January 28, 1999, at the Holiday Inn Coliseum, 630

Assembly Street, Columbia, SC, (803) 799-7800. The first session begins

at 1:00 p.m. and the second begins at 6:00 p.m.

2. Tuesday, February 2 at the North Augusta Community Center, 495

Brookside Drive, North Augusta, SC, (803) 441-4290. The first session

begins at 1:00 p.m. and the second begins at 6:00 p.m.

ADDRESSES: Written comments, requests for further information on the

draft EIS or public meetings, and requests for copies of the document

should be directed to Andrew R. Grainger, NEPA Compliance Officer,

Savannah River Site, Building 742-A, Room 185, Aiken, South Carolina

29802; orally by calling (800) 881-7292; or electronically to

[email protected]. Addresses of locations where the Draft EIS is available

for public review are listed in this notice under ``Availability of

Copies of the Draft EIS.''

General information on the DOE National Environmental Policy Act

(NEPA) process may be requested from Ms. Carol Borgstrom, Director,

Office of NEPA Policy and Assistance (EH-42), U.S. Department of

Energy, 1000 Independence Avenue, SW, Washington, DC 20585. Ms.

Borgstrom may be contacted by telephone at (202) 586-4600 or by leaving

a message at 1-800-472-2756.

SUPPLEMENTARY INFORMATION:

Background

The U.S. Atomic Energy Commission, a DOE predecessor agency,

established the SRS in the early 1950s for the production of special

radioactive isotopes to support national programs. Historically, the

primary Site mission was the production of strategic isotopes

(plutonium-239 and tritium) for use in the development and production

of nuclear weapons. The SRS produced other isotopes (e.g., californium-

252, plutonium-238, and americium-241) to support research in nuclear

medicine, space exploration, and commercial applications. DOE produced

these isotopes in the five SRS production reactors.

The material used to produce isotopes consisted of nuclear fuel and

targets. The nuclear fuel was enriched uranium that was alloyed with

aluminum and then clad in aluminum. The targets were either oxides or

metallic forms of various isotopes such as neptunium-237 or uranium-238

that were clad with aluminum. Fuel and targets were fabricated at the

SRS and placed in the reactors and then the reactors operated to create

the neutrons necessary to transmute the target material. After

irradiation, the fuel and targets (collectively referred to as spent

nuclear fuel) were removed from the reactors and placed in water-filled

basins for short-term storage, about 12 to 18 months, before they were

chemically processed in the SRS separations facilities.

SNF was chemically dissolved in F or H Canyon to recover the

uranium or transuranic isotopes for future use (``reprocessing''). The

remaining residue from the fuel, high-level radioactive waste

consisting primarily of fission products and cladding in liquid form,

was transferred to large steel tanks for storage. The high-level waste

is being vitrified in the Defense Waste Processing Facility at the SRS

to prepare it for placement in a geologic repository.

In 1992, the Secretary of Energy directed that reprocessing

operations to produce strategic nuclear materials be phased out

throughout the DOE complex. However, unprocessed SNF and targets

remained in storage. SRS also has accepted SNF from foreign and

domestic research reactors. In the past, most of this material was

reprocessed. With the end of the Site's strategic nuclear materials

production mission, SNF from research reactors has been accumulating in

the Receiving Basin for Offsite Fuels and the L-Reactor Disassembly

Basin.

Stabilization

DOE has taken action to stabilize about 175 MTHM of the 195 MTHM of

aluminum-based SNF that was in storage at SRS in 1995. DOE decided to

stabilize this material following completion of the Interim Management

of Nuclear Materials Environmental Impact Statement (DOE/EIS-0220). The

primary purpose of the actions described in that environmental impact

statement (EIS) was to correct or eliminate potential health and safety

vulnerabilities related to some of the methods used to store nuclear

materials (including SNF) at SRS. In that EIS, DOE identified the

remaining 20 MTHM (out of 195 MTHM) of aluminum-based SNF at SRS as

``stable'' (i.e., the SNF likely could be safely stored for about 10

more years, pending decisions on final disposition). Thus, that 20 MTHM

of aluminum-based SNF is included in this EIS.

On June 1, 1995, DOE decided (60 FR 28680) under the Department of

Energy Programmatic Spent Nuclear Fuel Management and Idaho National

Engineering Laboratory Environmental Restoration and Waste Management

Programs Final Environmental Impact Statement to consolidate existing

and

[[Page 2202]]

newly generated SNF at three existing Departmental sites (including

SRS) based on the fuel type, pending future decisions on ultimate

disposition. DOE designated the SRS as the site that would manage

aluminum-based SNF. As a result, DOE will transfer 20 MTHM of non-

aluminum-based SNF from SRS to Idaho National Engineering and

Environmental Laboratory (INEEL) and will transfer about 5 MTHM of

aluminum-based SNF at INEEL to SRS. Additionally, SRS could receive

about 5 MTHM of aluminum-based SNF from domestic research reactors.

In May 1996, DOE announced a decision (61 FR 25092) under the Final

Environmental Impact Statement on a Proposed Nuclear Weapons

Nonproliferation Policy Concerning Foreign Research Reactor Spent

Nuclear Fuel to accept about 18 MTHM of aluminum-based SNF containing

uranium of U.S. origin from foreign research reactors for management in

the United States at the SRS. The receipt of foreign research reactor

SNF at SRS is now underway and receipts are scheduled to be completed

by 2009. The 18 MTHM of foreign research reactor SNF that could be

received at SRS is included in the scope of this EIS. (Recent decisions

by some foreign research reactor operators have reduced the quantity of

SNF expected to be shipped to SRS from about 18 MTHM to about 14 MTHM;

however, for this EIS the 18 MTHM projection is used because foreign

research reactor operators still have the option to ship to the United

States.) Table S-1 summarizes the amount of SNF to be managed at SRS

that is considered in this EIS.

Table 1.--Quantity of SNF Discussed in This EIS

------------------------------------------------------------------------

------------------------------------------------------------------------

Aluminum-based SNF stored at SRS............................. 20 MTHM

Domestic and DOE aluminum-based research reactor SNF to be

received at SRS............................................. 10 MTHM

Foreign Research Reactor aluminum-based SNF to be received at

SRS......................................................... 18 MTHM

Non-aluminum-based SNF at SRS (to be shipped to INEEL)....... 20 MTHM

------------------------------------------------------------------------

Purpose and Need for Action

DOE anticipates that it eventually will place most of its aluminum-

based SNF inventory in a geologic repository after treatment or

repackaging. DOE currently is conducting analysis leading to a decision

whether to recommend the Yucca Mountain site in Nevada as the site of

this nation's first geologic repository. Even if the Nuclear Regulatory

Commission eventually were to license such a site, DOE does not expect

a geologic repository to be available until at least 2010 and it is

unclear when shipments from DOE sites could begin. Regardless of when a

repository is available, the Department intends to develop and

implement a safe and efficient SNF management strategy that includes

preparing for ultimate disposition the aluminum-based SNF stored at SRS

or expected to be shipped to SRS. DOE is committed to avoiding

indefinite storage at the SRS of this nuclear fuel in a form that is

unsuitable for final disposition. Therefore, DOE needs to identify

management technologies and facilities for storing and treating this

SNF in preparation for final disposition.

Scope

In this EIS, DOE is evaluating the treatment and storage of about

48 MTHM of aluminum-based SNF pending shipment to a geologic

repository, including impacts from the construction and operation of

facilities (either new or modified existing facilities) that would be

used to receive, store, treat, and package SNF in preparation for

ultimate disposition.

Onsite transportation impacts are considered; however, no impacts

associated with transporting SNF to SRS are included, because these

impacts have been assessed in other EISs.

The potential impacts of transporting SNF to a geologic repository

are discussed for completeness but no decisions related to transporting

SNF offsite will be made under this EIS. Transportation of SNF to a

federal repository will be addressed in the EIS for a Geologic

Repository for the Disposal of Spent Nuclear Fuel and High-Level

Radioactive Waste at Yucca Mountain, Nye County, Nevada (Notice of

Intent published in 60 FR 40164 on August 7, 1995). The Yucca Mountain

EIS is being prepared in the event DOE decides to recommend Yucca

Mountain as the site of the Nation's first geologic repository for SNF

and high-level radioactive waste.

DOE also evaluates transferring 20 MTHM of non-aluminum-clad spent

nuclear fuel currently stored in the Receiving Basin for Offsite Fuel

at SRS to a new dry storage facility at SRS. This transfer would occur

only if a dry storage facility were built as part of the implementation

of a treatment technology to prepare aluminum-based spent nuclear fuel

for disposition and if the dry storage facility became operational

before the non-aluminum-clad fuel was transferred to the INEEL. The

transfer to dry storage would occur after the fuel had been relocated

from the Receiving Basin for Offsite Fuel to the L-Reactor Disassembly

Basin in support of activities necessary to phase out the use of the

Receiving Basin for Offsite Fuel by 2006.

This EIS does not evaluate the impacts of managing the non-

aluminum-clad fuel at INEEL or of transporting the fuel to INEEL. These

impacts were considered in the SNF programmatic EIS which served as the

basis for DOE's decision to consolidate the storage of non-aluminum-

clad spent nuclear fuel at the INEEL.

Additionally, in this EIS DOE evaluates alternative storage

arrangements for Mark-51 and ``other'' targets currently located in the

Receiving Basin for Offsite Fuel at the SRS. In addition to evaluating

the continued use of wet storage, DOE considers transferring the

targets to dry storage to provide flexibility in material management

operations. The targets contain americium and curium isotopes that have

potential programmatic use.

Decisions To Be Based on This EIS

DOE expects to make the following decisions on the management of

SNF and preparation of SNF for ultimate disposition.

Select the appropriate treatment or packaging technology

to prepare for ultimate disposal of the aluminum-based SNF that is to

be managed at SRS.

Determine whether DOE should construct new facilities or

use existing facilities to store and treat or package aluminum-based

SNF that is expected to be managed at SRS in preparation for its

ultimate disposition.

Determine whether DOE should repackage and dry-store

stainless-steel and zirconium-clad SNF pending shipment to INEEL, and

whether DOE should repackage and dry-store americium/curium targets

pending decisions on programmatic use. Repackaging and dry-storing

these fuels would further DOE's plan to phase out the use of the

Receiving Basin for Offsite Fuel at the SRS.

Proposed Action

DOE's proposed action is to safely manage SNF that is currently

located or expected to be received at SRS, including treating or

packaging aluminum-based fuel for offsite shipment and placement in a

monitored geologic repository, and packaging non-aluminum-clad fuel and

programmatic material for dry storage.

In the Record of Decision for the Foreign Research Reactor EIS (61

FR 25092--May 17, 1996), DOE stated that it would embark on an

accelerated

[[Page 2203]]

program at SRS to identify, develop, and demonstrate one or more non-

reprocessing, cost effective treatment or packaging technologies to

prepare aluminum-based foreign research reactor spent nuclear fuel for

ultimate disposition.

Based on that decision, DOE's strategy is to select a new non-

chemical processing technology or a new packaging technology that would

put aluminum-based foreign research reactor SNF into a form or

container suitable for direct placement in a monitored geologic

repository. The SNF would be treated or conditioned to address

potential repository acceptance criteria or safety concerns. After

implementing the new non-chemical processing treatment or packaging

technology, DOE would manage the SNF in a road-ready condition at SRS

in dry storage pending shipment to a geologic repository.

Because of the similarity of the materials, DOE proposes to manage

the other aluminum-alloy SNF that is the subject of this EIS (domestic

research reactor and DOE reactor fuels) in the same manner as the

foreign research reactor fuels.

DOE has included chemical processing as a management alternative in

this EIS. However, DOE's strategy and preference is to use non-chemical

separations processes when practical. DOE proposes to use chemical

separation processes when a potential health or safety vulnerability

exists for aluminum-based SNF that DOE considers should be alleviated

before a non-chemical separations process is in operation in about

2005. Additionally, such SNF in its current form would likely not be

acceptable in a geologic repository.

Alternatives Considered

For analysis in this EIS, DOE has categorized the SNF at SRS into

six groups based on characteristics such as fuel size, physical or

chemical properties, and radionuclide inventories. To manage this SNF

and prepare it for disposition, DOE identified six reasonable new

technologies and one existing technology (conventional chemical

processing) for analysis. Because of the differences in the

characteristics of the SNF and the capabilities of the technologies, no

single technology could be applied to all the SNF. Although there are

many possible combinations of technologies and fuel groups, DOE

evaluated a limited number of configurations as alternatives. The

alternatives were chosen to illustrate the range of impacts that could

occur and consist of: Preferred Alternative, Minimum Impact

Alternative, Direct Disposal Alternative, Maximum Impact Alternative,

and the No Action Alternative.

In the Preferred Alternative, DOE proposes to implement several

technologies to manage the SNF at SRS. These include Melt and Dilute,

Conventional Processing, and Repackage and Prepare to Ship. The Melt

and Dilute option is the preferred method for treating most (about 97

percent by volume and 60 percent by mass) of the spent nuclear fuel.

Conventional processing would be used for the remaining 3 percent by

volume (40 percent by mass) because of the potential health and safety

vulnerability of continuing wet storage of those fuels while awaiting

the availability of Melt and Dilute technology and uncertainties

associated with repository acceptance. DOE would continue to wet store

the Higher Actinide Targets and the non-aluminum clad SNF. If this

material has not been transferred offsite by the time a dry storage

facility is in operation at the SRS, DOE could repackage this material

and transfer it to dry storage.

Availability of Copies of the Draft EIS

Copies of the Draft EIS are being distributed to Federal, State and

local officials and agencies; Tribes; and organizations and individuals

that have indicated an interest in SRS or the Draft EIS. In addition,

the Draft EIS is available on the Internet at the following address:

http://www.eh.doe.gov/nepa/docs/docs.htm. Addresses of DOE Public

Reading Rooms and libraries where the Draft EIS will be available for

public review are listed below:

Freedom of Information Public Document Room, University of South

Carolina at Aiken, SC, Gregg-Graniteville Library, 471 University

Parkway, Aiken, SC 29801

Freedom of Information Reading Room, U.S. Department of Energy, Room

1E-190, Forrestal Building, 1000 Independence Avenue, SW, Washington,

DC 20585

Battelle-Pacific Northwest Laboratories, Technical Library, P.O. Box

999, Richland, WA 99352

Pullen Public Library, 100 Decatur Street, SE, Atlanta, GA 30303

Reese Library, Augusta College, 2500 Walton Way, Augusta, GA 30904

Georgia Institute of Technology, Bobby Dodd Way, Atlanta, GA 30332

Chatham-Effingham-Liberty Regional Library, 2002 Bull Street, Savannah,

GA 31499-4301

Los Alamos Technical Association, 1200 Trinity Drive, Los Alamos, NM

87544

U.S. Department of Energy, FOIA Reading Room, 4700 Morris NE,

Albuquerque, NM 87111

U.S. Department of Energy, Albuquerque Operations Office, National

Atomic Museum, 20358 Wyoming Boulevard SE, Kirtland Air Force Base,

P.O. Box 5400, Albuquerque, NM 87185

The Libraries, Colorado State University, Fort Collins, CO 80523

Erskine College, McCain Library, One Depot Street, Due West, SC 29639

Parsons Brinckeroff Library, 1660 Lincoln Street, Suite 2000, Denver,

CO 80264

Public Reading Room, Chicago Operations Office, 9800 South Cass Avenue,

Argonne, IL 60439

Argonne National Laboratory, Technical Library, P.O. Box 2528, Idaho

Falls, ID 83403

Library of Congress, CRS-STR-LM413, Washington, DC 20540-7490

South Carolina State Library, 1500 Senate Street, Columbia, SC 29211

County Library, 404 King Street, Charleston, SC 29403

Savannah River Site Library, Savannah River Technology Center, 773-A,

Savannah River Site, Aiken, SC 29808

Westinghouse Savannah River Site Company Library, 766-H, Savannah River

Site, Aiken, SC 29808

U.S. Department of Energy, Public Reading Room, Oak Ridge Operations

Office, 55 Jefferson Circle, Room 1123, Oak Ridge, TN 37831

Issued in Washington, DC on January 7, 1999.

David G. Huizenga,

Acting Deputy Assistant Secretary for Nuclear Material and Facility

Stabilization, Office of Environmental Management.

[FR Doc. 99-750 Filed 1-12-99; 8:45 am]

BILLING CODE 6450-01-P