Federal Register / Vol. 62, No. 204 / Wednesday, October 22, 1997 / Notices 54859

such statements should be sent to the

Executive Secretary of the Advisory

Council at the above address. Papers

will be accepted and included in the

record of the meeting if received on or

before October 30.

Signed at Washington, D.C. this 15th day

of October, 1997.

Olena Berg,

Assistant Secretary, Pension and Welfare

Benefits Administration.

[FR Doc. 97–27956 Filed 10–2–97; 8:45 am]

BILLING CODE 4510–29–M

DEPARTMENT OF LABOR

Pension and Welfare Benefits

Administration

100th Full Meeting of the Advisory

Council on Employee Welfare and

Pension Benefits Plans; Notice of

Meeting

Pursuant to the authority contained in

Section 512 of the Employee Retirement

Income Security Act of 1974 (ERISA), 29

U.S.C. 1142, the 100th public meeting

will be held November 13, 1997 of the

Advisory Council on Employee Welfare

and Pension Benefit Plans.

The session will take place in the

Secretary’s Conference Room S–2508,

U.S. Department of Labor Building,

Second and Constitution Avenue, NW,

Washington, D.C. 20210. The purpose of

the open meeting, which will run from

1:00 p.m. until approximately 2:30 p.m.,

is for working group chairs and vice

chairs to present their groups’ final

reports and recommendations of the

year to the full Council for its action on

their findings and/or acceptance before

the reports and recommendations are

officially forwarded to the Secretary of

Labor. The meeting also will provide the

opportunity for an update on activities

of the Pension and Welfare Benefits

Administration by the Assistant

Secretary of that organization and for a

formal ceremony of appreciation for

outgoing members of the Council.

Members of the public are encouraged

to file a written statement pertaining to

the Council’s specific topics for the year

by submitting 20 copies on or before

October 30, 1997, to Sharon Morrissey,

Executive Secretary, ERISA Advisory

Council, U.S. Department of Labor,

Room N–5677, 200 Constitution

Avenue, NW, Washington, D.C. 20210.

Individuals or representatives of

organizations wishing to address the

Council should forward their request to

the Executive Secretary or telephone

(202) 219–8753. Oral presentations will

be limited to 10 minutes, time

permitting, but an extended written

statement may be submitted for the

record. Individuals with disabilities,

who need special accommodations,

should contact Sharon Morrissey by

October 30, at the address indicated in

this notice.

Organizations or individuals may also

submit statements for the record

without testifying. Twenty (20) copies of

such statements should be sent to the

Executive Secretary of the Advisory

Council at the above address. Papers

will be accepted and included in the

record of the meeting if received on or

before October 30.

Signed at Washington, D.C. this 15th day

of October, 1997.

Olena Berg,

Assistant Secretary, Pension and Welfare

Benefits Administration.

[FR Doc. 97–27957 Filed 10–21–97; 8:45 am]

BILLING CODE 4510–29–M

NUCLEAR REGULATORY

COMMISSION

[Docket Nos. 50–369 and 50–370]

Duke Energy Corporation; Notice of

Consideration of Issuance of

Amendments to Facility Operating

Licenses, Proposed No Significant

Hazards Consideration Determination,

and Opportunity for a Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of amendments to

Facility Operating License Nos. NPF–9

and NPF–17 issued to Duke Energy

Corporation (the licensee) for operation

of the McGuire Nuclear Station, Units 1

and 2, located in Mecklenburg County,

North Carolina.

The proposed amendments would

revise Technical Specification Table

3.3–4, ‘‘Engineered Safety Features

[ESF] Actuation System Instrument Trip

Setpoints.’’ Specifically, the

amendments would support the

replacement of the three safety-related

wide range level instruments. The ESF

trip setpoint for the refueling water

automatic switch over to recirculation

would be revised to account for the

difference in instrument uncertainty

associated with wide range level

instruments and provide additional

operator response time margin.

Before issuance of the proposed

license amendment, the Commission

will have made findings required by the

Atomic Energy Act of 1954, as amended

(the Act) and the Commission’s

regulations.

The Commission has made a

proposed determination that the

amendment request involves no

significant hazards consideration. Under

the Commission’s regulations in 10 CFR

50.92, this means that operation of the

facility in accordance with the proposed

amendment would not (1) involve a

significant increase in the probability or

consequences of an accident previously

evaluated; or (2) create the possibility of

a new or different kind of accident from

any accident previously evaluated; or

(3) involve a significant reduction in a

margin of safety. As required by 10 CFR

50.91(a), the licensee has provided its

analysis of the issue of no significant

hazards consideration, which is

presented below:

First Standard

Operation of the facility in accordance

with the proposed amendment will not

involve a significant increase in the

probability or consequences of an accident

previously evaluated.

Probability

The FWST [Refueling Water Storage Tank]

and its associated instrumentation are not

considered accident initiators. The

instrumentation change is from a narrow

range type instrument to a wide range type

instrument. A failure of either type of

instrument could result in an undesired

switch over or failure to switchover.

However, the failure could not initiate any

subsequent accident sequences.

Consequences

With the switchover to recirculation

setpoint change, the system design will still

provide enough injected water to ensure that

the reactor remains shut down, as well as

provide sufficient water depth within the

containment sump to ensure adequate net

positive suction head (NPSH) for the ECCS

[emergency core cooling system] pumps and

protect against vortexing. Also, adequate time

is provided to ensure the completion of all

operator actions necessary for switchover to

cold leg recirculation prior to the loss of all

usable FWST inventory and loss of suction

to the ECCS pumps.

The change in the FWST LOW level

setpoint reduces the FWST volume that is

delivered to the primary system in the

injection phase of a LOCA [loss-of-coolant

accident]. Thus, this volume reduction

affects the containment pressure response

during a LOCA. A reanalysis of the

containment pressure response using the

NRC-approved methodology of DPC–NE–

3004 demonstrates that the peak containment

pressure remains below the design limit for

the proposed FWST LOW level setpoint.

The LOCA blowdown, refill, and reflood

phases of the analysis are not affected by the

change in switchover setpoint. Therefore, the

fuel clad integrity will not be impacted as a

result of this change. The containment

response was analyzed and found to be

within acceptable limits. Therefore, the

fission product barriers are unaffected by this

change in setpoint.

The radiological calculations include

assumptions regarding the start of ECCS

recirculation which could be impacted by