18154 Federal Register / Vol. 60, No. 68 / Monday, April 10, 1995 / Notices

minus 10 months during each 10-year

service period.

Environmental Impacts of the Proposed

Action

The proposed exemption would not

adversely affect primary containment

integrity. The three required Type A

tests would still be conducted within

the 10-year service period while giving

the licensee flexibility in scheduling

consistent with Diablo Canyon’s 18-

month fuel cycles. The combination of

the Appendix J requirement and the

current Diablo Canyon Technical

Specification requirement would

necessitate that the licensee, because of

Diablo Canyon’s 18-month fuel cycles,

perform Type A tests at the second and

fourth refueling outages but then would

not permit the third Type A test to be

conducted on a schedule that meets

both requirements. The Commission has

completed its evaluation of the

proposed action and concludes that the

intent of Section III.D.1.(a) of appendix

J that containment leak-tight integrity be

verified periodically throughout service

lifetime is met when licensees perform

three sets of Type A tests at

approximately equal intervals over the

10-year service period. Therefore, the

change will not increase the probability

or consequences of accidents, no

changes are being made in the types or

amounts of any effluents that may be

released offsite, and there is no

significant increase in the allowable

individual or cumulative occupational

radiation exposure. Accordingly, the

Commission concludes that there are no

significant radiological environmental

impacts associated with the proposed

action.

With regard to potential

nonradiological impacts, the proposed

action involves features located entirely

within the restricted area as defined in

10 CFR part 20. It does not affect

nonradiological plant effluents and has

no other environmental impact.

Accordingly, the Commission concludes

that there are no significant

nonradiological environmental impacts

associated with the proposed action.

Alternatives to the Proposed Action

Since the commission has concluded

there is no measurable environmental

impact associated with the proposed

action, any alternatives with equal or

greater environmental impact need not

be evaluated. As an alternative to the

proposed action, the staff considered

denial of the proposed action. Denial of

the application would result in no

change in current environmental

impacts and would result in a larger

expenditure of licensee resources to

perform a fourth Type A test within a

10-year service period. The

environmental impacts of the proposed

action and the alternative action are

similar.

Alternative Use of Resources

This action does not involve the use

of any resources not previously

considered in the Final Environmental

Statement for Diablo Canyon Nuclear

Power Plant, Unit Nos. 1 and 2.

Agencies and Persons Consulted

In accordance with its stated policy,

on February 16, 1995, the staff

consulted with the California State

official, Mr. Hank Kocol of the

Department of Health Services,

regarding the environmental impact of

the proposed action. The State official

had not comments.

Finding of No Significant Impact

Based upon the environmental

assessment, the Commission concludes

that the proposed action will not have

a significant effect on the quality of the

human environment. Accordingly, the

Commission has determined not to

prepare an environmental impact

statement for the proposed action.

For further details with respect to the

proposed action, see the licensee’s letter

dated February 16, 1994, which is

available for public inspection at the

Commission’s Public Document Room,

the Gelman Building, 2120 L Street,

NW., Washington, DC, and at the local

public document room located at the

California Polytechnic State University,

Robert E. Kennedy Library, Government

Documents and Maps Department, San

Luis Obispo, California 93407.

Dated at Rockville, Maryland, this 31st day

of March 1995.

For the Nuclear Regulatory Commission.

Theodore R. Quay,

Director, Project Directorate IV–2, Division

of Reactor Projects III/IV, Office of Nuclear

Reactor Regulation.

[FR Doc. 95–8706 Filed 4–7–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–322]

Environmental Assessment and

Finding of No Significant Impact

Regarding Termination of the

Shoreham Nuclear Power Station,

Nuclear Power Facility License No.

NPF–82

The U.S. Nuclear Regulatory

Commission is considering the issuance

of an Order modifying the June 11,

1992, Order (the decommissioning

Order) that authorized the Long Island

Power Authority (LIPA or the licensee)

to decommission the Shoreham Nuclear

Power Station (SNPS), Unit 1, at Wading

River, New York. The SNPS is located

in the town of Brookhaven, Suffolk

County, New York, about 50 miles east

of New York City, on the north shore of

Long Island. The modifying Order

would terminate License No. NPF–82

and release the site for unrestricted use

based on the successful completion of

decommissioning.

Environmental Assessment

Identification of Proposed Action

By letter dated June 27, 1991, the

former licensee, Long Island Lighting

Company (LILCO), and supplemented

by letter dated August 4, 1994, the

current licensee, LIPA, requested

termination of the SNPS, Nuclear Power

Facility (NPF) License No. NPF–82

(Docket No. 50–322). NRC approved, by

Order dated June 11, 1992, the

decommissioning of the SNPS. The June

11, 1992, Order contained the staff’s

Environmental Assessment and Finding

of No Significant Impact related to the

decommissioning of SNPS.

The licensee has completed the

decommissioning and Final

Termination Surveys of the SNPS.

Representatives of the Oak Ridge

Institute for Science and Education

(ORISE), under contract to NRC,

conducted a series of independent

confirmatory surveys, during four site

visits from February 1993 through

November 1994. The proposed action

would be to terminate the SNPS License

No. NPF–82 and release the facility and

site for unrestricted use.

The Need for the Proposed Action

To release the SNPS for unrestricted

access and use, License No. NPF–82

must be terminated.

Environmental Impact of License

Termination

In June 1992, NRC approved, by

Order, the decommissioning of the

SNPS. The June 11, 1992, Order

contained the staff’s Environmental

Assessment and Finding of No

Significant Impact related to the

decommissioning of SNPS.

Based on an agreement between the

Philadelphia Electric Company (PECo)

and LIPA, the slightly irradiated fuel

stored in the SNPS spent fuel pool was

transferred to the Limerick Generating

Station for use. The dismantlement and

decontamination of the SNPS began in

June 1992 and was completed in

accordance with an approved

decommissioning plan (DP), as

supplemented, in August 1994. All
Federal Register / Vol. 60, No. 68 / Monday, April 10, 1995 / Notices 18155

contaminated waste generated during

the SNPS decommissioning has been

removed from the site.

The approved DP, as supplemented,

contained the SNPS Final Termination

Survey Plan (Plan). The Plan described

the methods used by the licensee to

demonstrate compliance with existing

NRC unrestricted release criteria. The

guidelines used by the licensee for

residual radioactivity at the SNPS are

consistent with the values provided in

Table 1, of Regulatory Guide 1.86,

which establishes acceptable residual

surface contamination levels. NRC

authorized alternative contamination

limits for iron-55 and tritium above

those specified in Regulatory Guide

1.86. These alternative criteria were

presented to the Commission in SECY

94–145 and increased the allowable

residual average and maximum total

residual beta activity levels for iron-55

and tritium from 5000 average total and

15,000 maximum total (fixed plus

removable) disintegrations per minute

(dpm)/100 square centimeters to

200,000 average total and 600,000

maximum total dpm/100 square

centimeters, respectively. This

permitted the licensee to safely retain

on site major portions of the reactor

bioshield wall that did not exceed the

gamma dose rate criterion or the surface

contamination limits for other isotopes,

but which would have required offsite

disposal under the original iron-55 and

tritium surface contamination limits of

Regulatory Guide 1.86. A concentration

limit for cobalt-60 in soil and other bulk

materials of 8 picocuries per gram was

also established. An average gamma

dose rate criterion of 5 uR per hour

above background, at a distance of 1

meter from indoor accessible surfaces,

was used. For outdoor surfaces,

individual gamma exposure rates are

not to exceed 10 uR per hour above

background at 1 meter.

The licensee implemented a phased

approach to its Final Termination

Surveys and completed final

radiological surveys in August 1994.

These survey measurements were

verified by the NRC contractor, ORISE.

The ORISE confirmatory surveys

confirmed that the licensee’s

measurements meet the existing criteria

for unrestricted release. Since the

existing unrestricted release criteria

have been met, there is no significant

radiological impact on the environment

from the release of the site.

With regard to potential nonradiological impacts, the proposed

action does not affect non-radiological

plant effluents and has no other

environmental impact. Therefore, the

NRC staff concludes no significant nonradiological impacts are associated with

the proposed action.

In accordance with 10 CFR part 51,

the Commission has determined that the

issuance of this termination Order is

procedural in nature and will have no

significant impact on the quality of the

human environment. The proposed

Order terminates the SNPS, Unit 1,

Facility License No. NPF–82.

Alternative to the Proposed Action

Since the NRC staff has concluded

that there are no environmental impacts

associated with the proposed action,

any alternative with equal or greater

environmental impacts need not be

evaluated.

Agencies and Persons Consulted

The licensee initiated the request for

termination of the SNPS License No.

NPF–82. The NRC staff reviewed the

request and representatives from ORISE

performed confirmatory surveys. The

staff consulted with the State of New

York regarding environmental impacts

of the proposed action, and the State did

not provide any comments.

Finding of No Significant Impact

NRC has determined not to prepare an

environmental impact statement for the

proposed action. Based on the foregoing

environmental assessment, NRC has

concluded that the issuance of an Order

will not have a significant effect on the

quality of the human environment.

For further details with respect to this

action, see: (1) The licensee’s request to

terminate the SNPC license presented in

letters dated June 27, 1991 (SNRC–

1818), and August 4, 1994 (LSNRC–

2178); (2) the Commission’s Order

approving decommissioning dated June

11, 1992; (3) the licensee’s Termination

Survey Final Report, Phase 1 (LSNRC–

2101), dated September 30, 1993; the

licensee’s Termination Survey Final

Report, Phase 2 (LSNRC–2144), dated

February 4, 1994; the licensee’s

Termination Survey Final Report, Phase

3 (LSNRC–2173), dated June 14, 1994;

the licensee’s Termination Survey Final

Report, Phase 4 (LSNRC–2184), dated

October 12, 1994; and (4) the ORISE

Final Confirmatory Reports dated July

1993, September 1994, and February

1995. These documents are available for

public inspection at the Commission’s

Public Document Room, the Gelman

Building, 2120 L Street, NW.,

Washington, DC 20555, and at the

Shoreham Wading River Public Library,

Route 25A, Shoreham, NY 11786.

Copies may be obtained upon request

addressed to the U.S. Nuclear

Regulatory Commission, Washington,

DC 20555, Attention: Director, Division

of Waste Management.

Dated at Rockville, Maryland, this 3rd day

of April, 1995.

For the 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. 95–8705 Filed 4–7–95; 8:45 am]

BILLING CODE 7590–01–M

Decommissioning of the Depleted

Uranium Impact Area of the Jefferson

Proving Ground, Madison, IN; Notice of

Intent To Prepare an Environmental

Impact Statement and To Conduct a

Scoping Process

AGENCY: Nuclear Regulatory

Commission.

ACTION: Notice of intent to prepare an

Environmental Impact Statement (EIS),

conduct a scoping process for the EIS,

and conduct a scoping meeting.

SUMMARY: The NRC intends to prepare

an Environmental Impact Statement for

the decommissioning of the depleted

uranium (DU) impact area (the Delta

Impact Area) of the Jefferson Proving

Ground (JPG), Madison, Indiana. The

DU impact area was used by the U.S.

Army, during the period of 1983–1994,

to perform testing of DU projectiles and

munitions in accordance with NRC

License No. SUB–1435. The U.S. Army

has requested an exemption (under 10

CFR 40.14) from NRC requirements in

10 CFR 40.4 to allow termination of the

license with land use restrictions on the

Delta Impact Area. This notice is to

inform the public and any concerned

parties of NRC’s intent to prepare an EIS

in conjunction with this proposed

action and to conduct a scoping process

that will include a public scoping

meeting.

DATES: Written comments on matters

covered by this notice received by June

9, 1995 will be considered in

developing the scope of the EIS.

Comments received after this date will

be considered if it is practical to do so,

but the NRC is able to assure

consideration only for comments

received on or before this date. A public

scoping meeting will be held at the

Madison Junior High School cafetorium

located on 701 Eighth Street, Madison,

Indiana. The scoping meeting will be

held on April 26, 1995, from 7 to 10

p.m.

ADDRESSES: Written comments on the

matters covered by this notice or the

scoping meeting should be sent to:

Rules Review and Directives Branch,