# Decommissioning of Shieldalloy Metallurgical Corporation's Facility in Cambridge, Ohio: Notice of Revision to the Scope of an Environmental Impact Statement

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URL: https://www.frixlaw.com/law-library/documents/fr%3A95-20639

## Record

- **Collection:** Federal Register
- **Document type:** Notice
- **Published:** August 21, 1995
- **Citation:** 60 FR 43477

## Text

NUCLEAR REGULATORY COMMISSION

Decommissioning of Shieldalloy Metallurgical Corporation's
Facility in Cambridge, Ohio: Notice of Revision to the Scope of an
Environmental Impact Statement

AGENCY: U.S. Nuclear Regulatory Commission.

ACTION: Notice of intent to revise the scope of an environmental impact
statement (EIS).

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) intends to revise
the scope of an EIS for decommissioning Shieldalloy Metallurgical
Corporation's

[[Page 43478]]
(SMC's) facility located in Cambridge, Ohio.

ADDRESSES: Documents referred to in this notice may be examined at the
Commission's Public Document Room (PDR), 2120 L Street (Lower Level),
NW. Washington, DC, or at the local PDR in the Guernsey County District
Public Library, 800 Steubenville Avenue, Cambridge, Ohio.

FOR FURTHER INFORMATION CONTACT: James E. Kennedy, Division of Waste
Management, Office of Nuclear Material Safety and Safeguards,
Washington, DC 20555, Telephone: 301-415-6668.

SUPPLEMENTARY INFORMATION:

Background

On November 28, 1993, the NRC published, in the Federal Register
(58 FR 62384) a Notice of Intent to prepare an EIS for the proposed
stabilization of slag piles containing radioactive waste, located at
the SMC, Cambridge, Ohio, facility, and to conduct scoping for the EIS.
NRC's requirements for EIS scoping are contained in 10 CFR 51.28 and
51.29. The scoping process included a public scoping meeting held in
Byesville, Ohio, on December 13, 1993. NRC also invited the public and
interested agencies, organizations, and individuals to submit written
suggestions and comments for consideration in the scoping process. The
EIS scoping process was described in a ``Summary Report'' published in
May 1994. The ``Summary Report'' identified five alternatives to be
considered in the EIS. These were: (1) Onsite stabilization and
disposal (the licensee's proposed action); (2) off site disposal; (3)
onsite separation processing with off site disposal; (4) onsite
dilution and disposal; and (5) no action.
In a possibly related matter, NRC determined, in 1993, that slag
from the site, when it was owned by Foote Mineral Company (FMC) may
have been used as fill at off site locations. To date, NRC inspections
have identified 17 locations with slag having elevated levels of
radioactivity. Radiation surveys and slag analyses that NRC conducted
in 1994 indicate that the slag does not pose an immediate health and
safety risk to residents. However, some action may be necessary at
specific locations, to minimize the long-term risk associated with the
slag. To determine the nature and extent of the off site slag
contamination, Cyprus Foote Mineral Company (CFMC) (successor to FMC),
is conducting an investigation. Any needed remediation will be based on
the CFMC's further measurements and analyses and NRC's subsequent
review of this information.1

\1\ Documents (letters and reports) related to the slag review
program are available for public review at the Guernsey County
District Public Library, 800 Steubenville Avenue, Cambridge, Ohio.
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In addition to the issues that fall under NRC's jurisdiction, there
are other environmental issues, associated with decommissioning the
Cambridge site, that are regulated by other State and Federal agencies,
including the U.S. Environmental Protection Agency, the Ohio
Environmental Protection Agency (OEPA), and the Ohio Department of
Health. As a result of these other environmental issues, SMC and CFMC
are conducting a remedial investigation/ feasibility study (RI/FS) for
the SMC, Cambridge, Ohio, facility. The RI/FS is in response to a
consent order for a preliminary injunction agreed to, in principle, by
OEPA, SMC, and CFMC. This RI/FS concerns the remediation of hazardous
wastes, industrial wastes, water pollution, and other wastes associated
with the Cambridge facility. Some of these wastes may be located in the
two slag piles. Because the RI/FS is expected to result in information
needed by NRC to develop the EIS, NRC staff is participating in
discussions between the companies and OEPA concerning the development
of the RI/FS for this site.
Revision to the Scope of the EIS

At meetings with the OEPA in December 1994, attended by NRC staff,
SMC representatives indicated that decommissioning alternatives under
consideration for the SMC, Cambridge, Ohio, facility should include the
relocation of off site slag that may have originated from this
facility. Because this new alternative would impact the EIS under
development by NRC, NRC staff requested a formal proposal from SMC
concerning the inclusion of this alternative, on January 5, 1995. In a
letter dated January 25, 1995, SMC requested that the EIS be modified
to include an analysis of the relocation of the off site slag to the
SMC, Cambridge, Ohio, site.
On April 20, 1995, PTI Environmental Services, Inc. (PTI), acting
on behalf of legal counsel for SMC and CFMC, submitted a Preliminary
Draft Feasibility Study (FS) for the SMC, Cambridge, site to OEPA. The
FS included additional information concerning this requested revision
to the scope of the EIS. In the discussion of this alternative, the FS
assumes that 10,000 yd \3\ of slag, that may have been produced at the
site and used off site, will be excavated and relocated to the West
Slag Pile. Only slag that was originally produced at the site and is
similar to slag in the West Slag Pile would be brought back onsite. The
FS estimates an area of 75,000 ft \2\ for the relocated slag. By
comparison, the existing West Slag Pile has an estimated volume of
approximately 220,000 yd \3\, covering an area of 359,000 ft \2\.
Because CFMC is still conducting the characterization of the off site
slag, the volume and radiological composition of this slag have not
been determined.
In addition, the preliminary draft FS identified additional site
remediation alternatives that would impact the scope of the EIS. These
additional alternatives involve the placement of wetland soils, onsite
sediments (from drainage ditches), and off site sediments (from Chapman
Run) on the West Slag Pile. SMC formally requested NRC staff to expand
the scope of the EIS to include these alternatives, in a letter dated
July 5, 1995. The preliminary draft FS estimates the volumes of each of
these materials to be approximately 26,000 yd \3\, 80 yd \3\, and 7,400
yd \3\, respectively. Radiological contamination of these materials is
not expected. The principal chemical contaminant is expected to be
vanadium.
Section 51.29(c) of the U.S. Code of Federal Regulations (Title 10)
states that the appropriate NRC staff director may, at any time before
the issuance of the draft EIS, revise the scoping determinations, as
appropriate, if substantial changes are made in the proposed action, or
if significant new circumstances or information arise that bear on the
proposed action or its impacts. Under the provisions of Section
51.29(c), the staff has determined that the licensee's proposed new
alternatives, concerning the relocation of the off site slag and the
disposal of wetland soils, onsite sediments, and off site sediments,
constitute a significant change in the proposed action. Therefore, the
staff intends to revise the scope of the EIS to examine the potential
environmental impacts of these alternatives, in addition to those
alternatives identified in the Scoping Process Summary Report. The
revised list of alternatives is described below.

Decommissioning Alternatives To Be Considered

1. Onsite stabilization and disposal (licensee's proposed action).
a. Without off site slag, soils, or sediments--Radioactive
contamination would be consolidated, stabilized, covered, and graded in
a manner to provide long-term protection against

[[Page 43479]]
wind and water erosion and to minimize ground water contamination. This
alternative would also likely include land use restrictions and/or
other institutional controls, to prevent or reduce potential intrusion
into the waste, to monitor the long-term effectiveness of the disposal,
and to take mitigative measures as necessary to protect the public and
environment.
b. With off site slag only--This alternative is similar to
Alternative 1.a, with the addition of approximately 10,000 yd \3\ of
off site slag to the West Pile before stabilization and capping.
c. With soils and sediments only--This alternative is similar to
Alternative 1.a, with the addition of approximately 33,500 yd \3\ of
chemically contaminated soils and sediments to the West Pile before
stabilization and capping.
d. With off site slag, soils, and sediments--This alternative is
similar to Alternative 1.b, with the addition of approximately 33,500
yd \3\ of chemically contaminated soils and sediments to the West Pile
before stabilization and capping.
2. Off site disposal--Radioactive contamination would be exhumed
from the site and disposed of off site at a licensed low-level waste
disposal facility. Radioactive contamination onsite would be reduced
down to levels that NRC presently considers acceptable for release for
unrestricted use (e.g., 10 picoCuries per gram (pCi/g) total uranium
(with decay products) and 10 pCi/g thorium-232 and thorium-228 and
other criteria such as exposure rate and radon concentrations).
3. Onsite separation processing with off site disposal--Radioactive
contamination would be processed using physical or chemical methods to
separate more highly concentrated contamination from lower
concentrations that could be stabilized onsite. Higher concentration
wastes would be sent off site to a licensed disposal facility.
Radioactive contamination onsite would be reduced down to levels that
NRC presently considers acceptable for release for unrestricted use.
4. Onsite dilution and disposal--Existing radioactive contamination
would be blended with clean fill, to reduce average concentrations of
uranium and thorium to levels that NRC presently considers acceptable
for release for unrestricted use. Diluted contamination would then be
graded onsite and released for unrestricted use.
5. No action--Radioactive contamination would be abandoned in its
present configuration without any additional processing or
stabilization. This alternative does not consider any protective
measures, such as land use restrictions or other institutional
controls, that might mitigate or prevent intrusion into the waste or
long-term release and transport of contamination in the environment.
(The no-action alternative is only included for the purpose of
comparison with the other alternatives.)
The EIS will evaluate these alternative decommissioning approaches
with respect to: (1) The incremental impact to workers, members of the
public, and the environment both radiological and non-radiological
resulting from each alternative; and (2) the costs associated with each
alternative. The EIS will also include a comparative evaluation of the
decommissioning approaches based on the associated impacts and costs.
The evaluation is described in great detail in the November 28, 1993,
Federal Register notice (58 FR 62384).

EIS Development Schedule

NRC intends to prepare and issue for public comment a draft EIS in
March 1996. The comment period would be for 90 days. The final EIS is
scheduled for publication in January 1997. This schedule has been
delayed because information resulting from the RI/FS is needed to
conduct the EIS analyses. Further delays may occur if needed
information is not submitted in a timely manner. Subsequent to
completion of the final EIS, the NRC would review and act on a license
amendment from the licensee requesting authorization for
decommissioning the site, including the decommissioning plan as
required in 10 CFR 40.42(d). Depending on the resolution of the
licensee's financial restructuring under Chapter 11 of the bankruptcy
code, the NRC may terminate or postpone development of the EIS.

Dated at Rockville, Maryland, this 14th day of August 1995.

For the U.S. Nuclear Regulatory Commission.
Michael F. Weber,
Chief, Low-Level Waste and Decommissioning Projects Branch, Division of
Waste Management, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 95-20639 Filed 8-18-95; 8:45 am]
BILLING CODE 7590-01-P

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Source: Frix Law Library, https://www.frixlaw.com/law-library/documents/fr%3A95-20639. Public record. Not legal advice.
