9056 Federal Register / Vol. 60, No. 32 / Thursday, February 16, 1995 / Notices

Name: Special Emphasis Panel in

Information, Robotics and Intelligent Systems

(1200).

Date and Time: March 9–10, 1985, 8:30

a.m. to 5:00 p.m.

Place: Doubletree Hotel, 300 Army Navy

Drive, Arlington, VA 22202.

Type of Meeting: Closed.

Contact Person: Dr. Howard Moraff, Acting

Deputy Division Director, Robotics and

Intelligence, Room 1115, National Science

Foundation, 4201 Wilson Blvd., Arlington,

VA 22230. Telephone: (703) 306–1928.

Purpose of Meeting: To provide advice and

recommendations concerning proposals

submitted to NSF for financial support.

Agenda: To review and evaluate Interactive

Systems Program Proposals as part of the

selection process for awards.

Reason for Closing: The proposals being

reviewed include information of a

proprietary or confidential nature, including

technical information; financial data, such as

salaries; and personal information

concerning individuals associated with the

proposals. These matters are exempt under 5

U.S.C. 552b(c), (4) and (6) of the Government

in the Sunshine Act.

Dated: February 13, 1995.

M. Rebecca Winkler,

Committee Management Officer.

[FR Doc. 95–3934 Filed 2–15–95; 8:45 am]

BILLING CODE 7555–01–M

Special Emphasis Panel in Materials

Research; Meeting

In accordance with the Federal

Advisory Committee Act (Pub. L. 92–

463 as amended), the National Science

Foundation Announces the following

meeting:

Name: Special Emphasis Panel in Materials

Research.

Date and Time: March 10, 1995, 8:30

a.m.—5 p.m.

Place: National Science Foundation, 4201

Wilson Boulevard, Room 1060, Arlington,

VA 22230.

Type of Meeting: Closed.

Contact Person: Dr. Norbert M. Bikales,

Program Director, Polymers; Dr. David L.

Nelson, Program Director, Solid State

Chemistry, Division of Materials Research,

Room 1065. National Science Foundation,

Arlington, VA 22230. Telephone (703) 306–

1839.

Purpose of Meeting: To provide advice and

recommendations concerning support for

DMR 1995 Faculty Early Career Development

(CAREER) Program proposals.

Agenda: Evaluation of proposals.

Reason for Closing: The proposals being

reviewed include information of a

proprietary or confidential nature, including

technical information, financial Data such as

salaries, and personal information

concerning individuals associated with the

proposals. These matters are exempt under 5

U.S.C. 552b.(c) (4) and (6) of the Government

in Sunshine Act.

Dated: February 13, 1995.

M. Rebecca Winkler,

Committee Management Officer.

[FR Doc. 95–3929 Filed 2–15–95; 8:45 am]

BILLING CODE 7555–01–M

Special Emphasis Panel in

Mathematical Sciences; Meeting

In accordance with the Federal

Advisory Committee Act (Pub. L. 92–

463, as amended), the National Science

Foundation announces the following

meeting.

Name: Special Emphasis Panel in

Mathematical Sciences (1204).

Date and Time: March 6–7, 1995; 8:30 a.m.

til 5 p.m.

Place: National Science Foundation, 4201

Wilson Boulevard, Rm 1020, Arlington, VA

22230.

Type of Meeting: Closed.

Contact Person: Dr. Joe Jenkins, National

Science Foundation, 4201 Wilson Boulevard,

Arlington, VA 22230 Telephone: (703) 306–

1870.

Purpose of Meeting: To provide advice and

recommendations concerning proposals

submitted to National Science Foundation for

financial support.

Agenda: To review and evaluate proposals

concerning Lie Groups and their

representation as part of the selection process

for awards.

Reason for Closing: The proposals being

reviewed include information of a

proprietary or confidential nature, including

technical information; financial data, such as

salaries; and personal information

concerning individuals associated with the

proposals. These matters are exempt under 5

U.S.C. 552b(c), (4) and (6) of the Government

in the Sunshine Act.

Dated: February 13, 1995.

M. Rebecca Winkler,

Committee Management Officer.

[FR Doc. 95–3931 Filed 2–15–95; 8:45 am]

BILLING CODE 7555–01–M

Advisory Panel for Presidential Faculty

Fellows; Meeting

In accordance with the Federal

Advisory Committee Act (Pub. L. 92–

463, as amended), the National Science

Foundation announces the following

meeting.

Name: Advisory Panel for Presidential

Faculty Fellows (#139).

Date and Time: March 7–8, 1995; 8:30 a.m.

to 5 p.m. both days.

Place: Room 375, National Science

Foundation, 4201 Wilson Boulevard,

Arlington, VA 22230.

Type of Meeting: Closed.

Contact Person: Dr. Margaret A.

Cavanaugh, Program Director, National

Science Foundation, 4201 Wilson Boulevard,

Arlington, VA 22230, Telephone: (703) 306–

1842.

Purpose of Meeting: To provbide advice

and recommendations concerning

nominations submitted to NSF for financial

support.

Agenda: To review and evaluate

nominations for the Presidential Faculty

Fellows Program.

Reason for Closing: The nominations being

reviewed include information of a

proprietary or confidential nature, including

technical information; and personal

information concerning individuals

associated with the proposals. These matters

are exempt under 5 U.S.C. 552 b(c) (4) and

(6) of the Government in the Sunshine Act.

Dated: February 13, 1995.

M. Rebecca Winkler,

Committee Management Officer.

[FR Doc. 95–3930 Filed 2–15–95; 8:45 am]

BILLING CODE 7555–01–M

NUCLEAR REGULATORY

COMMISSION

[Docket No. 50–219]

GPU Nuclear Corporation; Oyster

Creek Nuclear Generating Station

Environmental Assessment and

Finding of No Significant Impact

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. DPR–

16, issued to GPU Nuclear Corporation,

(the licensee), for operation of the

Oyster Creek Nuclear Generating

Station, located in Ocean County, New

Jersey.

Environmental Assessment

Identification of the Proposed Action

The proposed action would change

the setpoints of Technical Specification

2.3.D, ‘‘Reactor High Pressure, Relief

Valve Initiation’’ by increasing the

setpoint value by 15 psig for each of the

Electromatic Relief Valve (EMRVs) in

the Automatic Depressurization System.

The proposed action is in accordance

with the licensee’s application for

amendment dated June 15, 1994, as

supplemented by letter dated September

23, 1994, and November 3, 1994.

The Need for the Proposed Action

The proposed action is needed

because the ‘‘Bourden tube’’ type

pressure switches currently in use at

Oyster Creek experience drift, which

results in exceeding the existing ‘‘as

found’’ setpoint. Increasing the

specified setpoints by 15 psig will

provide for expanding the ‘‘as found’’

tolerance bands. Increasing these

tolerance bands serves to ensure that the

setpoints will remain within the

Technical Specification requirements
Federal Register / Vol. 60, No. 32 / Thursday, February 16, 1995 / Notices 9057

over a nominal 24 month operating

cycle.

Environmental Impacts of the Proposed

Action

The Commission has completed its

evaluation of the proposed action and

concludes that the licensee has

provided information supporting the

use of a 1.04 multiplier. This multiplier

is applied to pool dynamic loads

previously calculated for the plant

unique analysis report (PUAR), to

account for the EMRV setpoint increase

and to account for errors in calculations

of the PUAR loads due to use of an

incorrect EMRV flow rating. The staff

has reviewed the licensee’s basis for use

of the multiplier and finds it acceptable.

The staff also finds that the structural

analysis of the affected plant

components was adequately

conservative to demonstrate

acceptability of the EMRV setpoint

change.

The proposed amendment involves a

minor change in the operation of the

facility. The change will not increase

the probability or consequences of

accidents, no changes are being made in

the types 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 does involve 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. 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 the Oyster Creek Nuclear

Generating Station.

Agencies and Persons Consulted

In accordance with its stated policy,

the staff consulted with the New Jersey

State official regarding the

environmental impact of the proposed

action. The State official had no

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 June 15, 1994, as supplemented

by letters dated September 23, and

November 3, 1994, which are 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

Ocean County Library, 101 Washington

Street, Tows River, NJ 08753.

Dated at Rockville, Maryland, this 8th day

of February 1995.

For the Nuclear Regulatory Commission.

Phillip F. McKee,

Director, Project Directorate I–4, Division of

Reactor Projects—I/II, Office of Nuclear

Reactor Regulation.

[FR Doc. 95–3876 Filed 2–15–95; 8:45 am]

BILLING CODE 7590–01–M

[Docket No. 50–325]

Carolina Power & Light Co.; Facility

Operating License

Exemption

In the Matter of Carolina Power & Light

Co.; (Brunswick Steam Electric Plant, Unit 1).

I

The Carolina Power & Light Company

(the licensee), is the holder of Facility

Operating License Nos. DPR–71 and

DPR–62 which authorizes operation of

the Brunswick Steam Electric Plant

(BSEP or the facility), Units 1 and 2,

respectively, at steady state power levels

not in excess of 2436 megawatts

thermal. The facility consists of two

boiling water reactors located at the

licensee’s site in Brunswick County,

North Carolina. The license provides,

among other things, that BSEP is subject

to all rules, regulations and Orders of

the Nuclear Regulatory Commission (the

Commission) now and hereafter in

effect.

II

Section III.D.1.(a) of appendix J to 10

CFR part 50 requires the performance of

three Type A containment integrated

leakage rate tests at approximately equal

intervals during each 10-year service

period of the primary containment. The

third test of each set shall be conducted

when the plant is shutdown for the 10-

year inservice inspection of the primary

containment.

III

By letter dated November 22, 1994,

CP&L requested a one-time exemption

from the requirement to perform a set of

three Type A tests at approximately

equal intervals during each 10-year

service period of the primary

containment for the Brunswick Steam

Electric Plant, Unit 1 (BSEP–1). the

requested exemption would permit a

one-time extension of the second 10-

year service period by approximately 18

months (from the April 1995 refueling

outage to the September 1996 refueling

outage). The requested temporary relief

would permit the third test of the

second 10-year service period to

correspond with the end of the current

American Society of Mechanical

Engineers Boiler and Pressure Vessel

Code (ASME Code) inservice inspection

interval.

IV

Section III.D.1.(a) of appendix J to 10

CFR part 50 states that a set of three

Type A leakage tests shall be performed

at approximately equal intervals during

each 10-year service period.

The requirement to perform a set of

three Type A leakage rate tests at

approximately equal intervals during

each 10-year containment service period

provides assurance that containment

leakage will not exceed allowable

values. Type A leakage rate tests were

performed as required by appendix J

during the first 10-year containment

service period that ended in 1986.

Since the first 10-year service period

for BSEP–1 was not aligned with the

service period for BSEP–2, CP&L moved

the end date for the BSEP–1 back to

coincide with the BSEP–2 end date.

Therefore, the second 10-year service

period for BSEP–1 began on July 10,

1986. This caused the first BSEP–1 Type

A test for the second period to be

performed in May 1987, only 11 months

into the interval. The second Type A

test on BSEP–1 was performed within

the 40-month plus or minus 10-month

interval required by the Technical

Specifications.