7590 Federal Register / Vol. 60, No. 26 / Wednesday, February 8, 1995 / Notices

from multiple monitoring stations)

annual radiation exposure as follows:

Year (FY)

Average

readings

(mrem)

1994 .............................................. 0.4

1993 .............................................. 0.5

1992 .............................................. 0.2

1991 .............................................. 0.1

1990 .............................................. 0.1

1989 .............................................. 0.2

1988 .............................................. 0.2

1987 .............................................. 1.2

1986 .............................................. 1.8

1985 .............................................. 2.2

Annual airborne effluent releases

from the facility are given in the next

table. FY 94 is presented in two half

years periods because amendments to

10 CFR Part 20 became effective on

January 1, 1994, which changed the

regulatory limits for release

concentrations to the environment for

certain radionuclides. Total curies

released during FY 94 is comparable to

past years. The percent of Regulatory

Limit column represents the percent of

the regulatory limit for concentration of

radionuclides in air after taking into

account dilution from the release point.

Year (FY)

Stack

release

(curies)

% of

regulatory

limit

1/1/94 to 6/30/94 ............. 398 21.7

7/1/93 to 12/31/93 ........... 275 4.1

1993 ................................ 923 6.0

1992 ................................ 728 4.9

1991 ................................ 684 4.4

1990 ................................ 542 3.5

1989 ................................ 1529 9.8

1988 ................................ 2627 17

1987 ................................ 4223 30

1986 ................................ 3797 26

1985 ................................ 4076 26

Annual liquid effluent releases are as

follows:

Year (FY)

Total

activity

(curies)

1994 .................................................. 0.025

1993 .................................................. 0.007

1992 .................................................. 0.036

1991 .................................................. 0.121

1990 .................................................. 0.080

1989 .................................................. 0.110

1988 .................................................. 0.072

1987 .................................................. 0.098

1986 .................................................. 0.288

1985 .................................................. 0.099

Low level solid waste shipped from

the facility is given in cubic feet and

total activity in curies. Increased

shipments in FY 1994 and FY 1993

represent an effort by the licensee to

remove solid waste from the facility

before waste disposal site closures

prevented future shipments of low level

solid waste.

Year (FY) Cubic

feet

Total

activity

(curies)

1994 .................................. 457 0.925

1993 .................................. 210 0.218

1992 .................................. 127 0.011

1991 .................................. 116 0.125

1990 .................................. 192 0.035

1989 .................................. 135 0.053

1988 .................................. 60 0.003

1987 .................................. 112 0.082

1986 .................................. 75 0.097

1985 .................................. 120 0.067

These releases are well within

regulatory limits and will not have a

significant impact on the environment.

Releases for the proposed license

extension are estimated to continue at

levels well within regulatory limits.

Alternative Use of Resources

One alternative to the proposed

amendment request is to deny the

request. If the request is denied, the

MITR would be shut down or an

application for license renewal would

be developed and submitted before

expiration of the current license on May

7, 1996. Shutting the reactor down

would result in the loss of an

educational tool for the training of

students and the conduct of research in

many areas including medical therapy.

If the request is denied and the licensee

proposes to renew the license, resources

would have to be expended on the part

of the licensee and the Commission

sooner than if the request for license

extension is granted. Denial of the

application would result in no change

in current environmental impacts.

Agencies and Persons Consulted

The NRC staff consulted no other

agencies or persons in reviewing the

request from the licensee.

Finding of No Significant Impact

The Commission has determined not

to prepare an environmental impact

statement for the proposed action based

upon the foregoing environmental

assessment. The Commission concludes

that the proposed action will not have

a significant effect on the quality of the

human environment for the reasons set

out above.

For detailed information with respect

to this proposed action, see the

application for amendment dated March

31, 1994, as supplemented, the Safety

Evaluation prepared by the staff, the

Negative Declaration Regarding Facility

Operating License R–37 for the

Massachusetts Institute of Technology

Research Reactor dated July 23, 1975,

and the Environmental Impact

Appraisal for the Massachusetts

Institute of Technology Reactor dated

July 23, 1975. These documents are

available for public inspection at the

Commission’s Public Document Room,

2120 L Street, NW., Washington, D.C.

20555.

Dated at Rockville, Maryland, this 2nd day

of February 1995.

For the Nuclear Regulatory Commission.

Seymour H. Weiss,

Director, Non-Power Reactors and

Decommissioning Project Directorate,

Division of Project Support, Office of Nuclear

Reactor Regulation.

[FR Doc. 95–3087 Filed 2–7–95; 8:45 am]

BILLING CODE 7590–01–M

Advisory Committee on Reactor

Safeguards; Subcommittee Meeting on

Thermal Hydraulic Phenomena

The ACRS Subcommittee on Thermal

Hydraulic Phenomena will hold a

meeting on February 15 and 16, 1995,

Room T–2B3, 11545 Rockville Pike,

Rockville, Maryland.

The meeting will be closed to public

attendance to discuss Westinghouse

proprietary information pursuant to (5

U.S.C. 552b(c)(4)), with the exception of

a 1–2 hour session on Thursday,

February 16, 1995, that will be open to

the public.

The agenda for the subject meeting

shall be as follows:

Wednesday, February 15, 1995—8:30 a.m.

until the conclusion of business; and

Thursday, February 16, 1995—8:30 a.m.

until the conclusion of business.

The Subcommittee will continue its

review of the Westinghouse COBRA/

TRAC thermal hydraulic code. The

purpose of this meeting is to gather

information, analyze relevant issues and

facts, and to formulate proposed

positions and actions, as appropriate,

for deliberation by the full Committee.

Oral statements may be presented by

members of the public with the

concurrence of the Subcommittee

Chairman; written statements will be

accepted and made available to the

Committee. Electronic recordings will

be permitted only during those portions

of the meeting that are open to the

public, and questions may be asked only

by members of the Subcommittee, its

consultants, and staff. Persons desiring

to make oral statements should notify

the cognizant ACRS staff engineer

named below five days prior to the

meeting, if possible, so that appropriate

arrangements can be made.
Federal Register / Vol. 60, No. 26 / Wednesday, February 8, 1995 / Notices 7591

During the initial portion of the

meeting, the Subcommittee, along with

any of its consultants who may be

present, may exchange preliminary

views regarding matters to be

considered during the balance of the

meeting.

The Subcommittee will then hear

presentations by and hold discussions

with representatives of the

Westinghouse Electric Corporation, NRC

staff, their consultants, and other

interested persons regarding this review.

Further information regarding topics

to be discussed, whether the meeting

has been cancelled or rescheduled, the

Chairman’s ruling on requests for the

opportunity to present oral statements

and the time allotted therefor can be

obtained by contacting the cognizant

ACRS staff engineer, Mr. Paul A.

Boehnert (telephone 301/415–8065)

between 7:30 a.m. and 4:15 p.m. (EST).

Persons planning to attend this meeting

are urged to contact the above named

individual one to two working days

prior to the meeting to be advised of any

potential changes in the proposed

agenda, etc., that may have occurred.

Dated: February 1, 1995.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 95–3090 Filed 2–7–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket Nos. 50–361 and 50–362]

Southern California Edison Co.; San

Diego Gas and Electric Co.; the City of

Riverside, California; the City of

Anaheim, California; and San Onofre

Nuclear Generating Station, Units Nos.

2 and 3

Notice is hereby given that the United

States Nuclear Regulatory Commission

(the Commission) is considering

approval under 10 CFR 50.80 of the

proposed corporate restructuring of San

Diego Gas & Electric Company (SDG&E),

one of the co-owners of San Onofre

Nuclear Generating Station, Units 2 and

3. By letter dated November 11, 1994,

Richard A. Meserve of Covington &

Burling, Counsel for SDG&E, informed

the Commission that a corporate

restructuring of SDG&E has been

proposed that will result in the creation

of a holding company under the

temporary name SDO Parent Co., Inc.

(‘‘Parent Company’’) of which SDG&E

would become a subsidiary. Under the

restructuring, the holders of SDG&E

common stock will become the holders

of common stock of the Parent Company

on a share-by-share basis. After the

restructuring, SDG&E will continue to

be a public utility providing the same

utility services as it did immediately

prior to the reorganization. SDG&E will

continue to be a licensee of the San

Onofre units, and no transfer of the

operating licenses or interests in the

units will result from the restructuring.

Control of the operating licenses for the

San Onofre units, now held by SDG&E

and its co-owners, will remain with

SDG&E and the same owners and will

not be affected by the restructuring.

Pursuant to 10 CFR part 80, the

Commission may approve the transfer of

control of a license, after notice to

interested persons. Such action is

contingent upon the Commission’s

determination that the holder of the

license and the transfer of such control

is otherwise consistent with applicable

provisions of law, regulations, and

orders of the Commission.

Dated at Rockville, Maryland, this 31st day

of January 1995.

Mel B. Fields,

Project Manager, Project Directorate IV–2,

Division of Reactor Projects III/IV, Office of

Nuclear Reactor Regulation.

[FR Doc. 95–3088 Filed 2–7–95; 8:45 am]

BILLING CODE 7590–01–M

Advisory Committee on Nuclear

Waste; Notice of Meeting

The Advisory Committee on Nuclear

Waste (ACNW) will hold its 71st

meeting on February 21–22, 1995, in

Room T–2B3, 11545 Rockville Pike,

Rockville, Maryland. The entire meeting

will be open to public attendance, with

the exception of portions that may be

closed to discuss information the release

of which would constitute a clearly

unwarranted invasion of personal

privacy pursuant to 5 U.S.C. 552b(c)(6)

and to project information provided in

confidence by a foreign source pursuant

to 5 U.S.C. 552b(c)(4).

The agenda for the subject meeting

shall be as follows:

Tuesday, February 21, 1995—8:30 A.M.

until 6:00 P.M.

Wednesday, February 22, 1995—8:30

A.M. until 6:00 P.M.

During this Meeting the Committee

plans to consider the following:

A. Proposed EPA Standards for Land

Disposal of Low-Level Radioactive

Waste—The Committee will hear

presentations and hold discussions with

representatives of the Environmental

Protection Agency and NRC staff on the

pre-proposal version of a standard for

land disposal of low-level waste. The

emphasis will be on commercial

disposal.

B. Meet with the Director, NRC’s

Division of Waste Management, NMSS—

The Director will provide information to

the Committee on current waste

management issues: issues may include

groundwater travel time associated with

a mined geologic disposal system, a

branch technical position on low-level

radioactive waste and key technical

uncertainties associated with high-level

waste disposal.

C. Review Draft Regulatory Guide DG–

3009—The Committee will review,

‘‘Topical Guidelines For The Licensing

Support System.’’ The Licensing

Support System is an electronic

information management system

designed to provide for the entry of the

access to potentially relevant licensing

information.

D. Model Validation—The NRC staff

will discuss perspectives from a joint

coordination effort between the NRC

and the Swedish Nuclear Power

Inspectorate on validation strategies for

computer models and conceptual

models. Portions may be closed to

protect information provided in

confidence by a foreign source pursuant

to 5 U.S.C. 552b(c)(4).

E. Preparation of ACNW Reports—

The Committee may prepare reports on

issues considered during this meeting

and possible additional topics such as

safety goals applicable to nuclear waste

disposal and generic issues involving

the direction of radioactive waste

research.

F. Lessons Learned From the Attempt

to Site a Low-Level Radioactive Waste

Disposal Facility in Martinsville,

Illinois—The Committee will hold a

discussion with individuals formerly

associated with the Illinois Siting

Commission to gain their perspective on

the Martinsville experience.

G. Meeting with NRC Commissioner

de Planque—The Committee will meet

with Commissioner de Planque to

discuss items of interest. Topics might

include: the use of multipurpose

canisters in high-level radioactive waste

disposal, the role of expert judgment in

high-level waste disposal, and DOE’s

program approach for site suitability at

Yucca Mountain.

H. Meeting with the Director, NRC’s

Office of Nuclear Regulatory Research—

The Committee will take part in a

discussion with the Director on his

vision of safety research over the

coming ten years with a focus on

radioactive waste disposal.

I. Committee Activities/Future

Agenda—The Committee will consider

topics proposed for future consideration

by the full Committee and working

groups. The Committee will also discuss

organizational and personnel matters

related to ACNW members and ACNW

staff. A portion of this session may be