Federal Register / Vol. 60, No. 74 / Tuesday, April 18, 1995 / Notices 19417

Signed at Washington, D.C., this 7th day of

April 1995.

Victor J. Trunzo,

Program Manager, Policy and Reemployment

Services, Office of Trade Adjustment

Assistance.

[FR Doc. 95–9563 Filed 4–17–95; 8:45 am]

BILLING CODE 4510–30–M

NATIONAL AERONAUTICS AND

SPACE ADMINISTRATION

[Notice 95–028]

NASA Advisory Council, Earth

Systems Science and Applications

Advisory Committee (ESSAAC);

Meeting

AGENCY: National Aeronautics and

Space Administration.

ACTION: Notice of Meeting.

SUMMARY: In accordance with the

Federal Advisory Committee Act, Public

Law 92–463, as amended, the National

Aeronautics and Space Administration

announces a forthcoming meeting of the

NASA Advisory Council, Earth Systems

Science and Applications Advisory

Committee.

DATES: May 17, 1995, 8:30 a.m. to 5:30

p.m.; and May 18, 1995, 8:30 a.m. to

5:30 p.m..

ADDRESSES: National Aeronautics and

Space Administration, MIC–7

Conference Room, 300 E Street, S.W.,

Washington, DC 20546.

FOR FURTHER INFORMATION CONTACT:

Dr. Robert A. Schiffer, Code YS,

National Aeronautics and Space

Administration, Washington, DC 20546,

(202) 358–1876.

SUPPLEMENTARY INFORMATION: The

meeting will be open to the public up

to the seating capacity of the room. The

provisional agenda for the meeting is as

follows: NASA Response to ESSAAC

Recommendations; impact of NASA

Streamlining on MTPE Science

Program; the MTPE Strategic Plan;

committee discussion; and findings,

conclusions, and recommendations.

It is imperative that the meeting be

held on these dates to accommodate the

scheduling priorities of the key

participants. Visitors will be requested

to sign a visitor’s register.

Dated: April 12, 1995.

Danalee Green,

Chief, Management Controls Office.

[FR Doc. 95–9484 Filed 4–17–95; 8:45 am]

BILLING CODE 7510–01–M

NUCLEAR REGULATORY

COMMISSION

[Docket No. 50–412]

Duquesne Light Company; Ohio

Edison Company; The Cleveland

Electric Illuminating Company; The

Toledo Edison Company; Notice of

Consideration of Issuance of

Amendment to Facility Operating

License, Proposed No Significant

Hazards Consideration Determination,

and Opportunity for a Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. NPF–

73, issued to Duquesne Light Company,

et al., (the licensee), for operation of the

Beaver Valley Power Station, Unit 2

(BVPS–2), located in Beaver County,

Pennsylvania.

The proposed amendment would

revise Technical Specification (TS)

4.6.2.2.d to delete the reference to the

specific test acceptance criteria for the

Containment Recirculation Spray

Pumps and replace the specific test

acceptance criteria with reference to the

requirements of the Inservice Testing

(IST) Program. In addition, the 18-

month test frequency would be replaced

with the test frequency requirements

specified in the IST Program. The

current footnote (1) pertaining to the

performance of recirculation spray

pump 2RSS*P21A would be deleted.

This proposed amendment is

requested to be processed as an exigent

TS change in accordance with 10 CFR

50.91(a)(6). Exigent processing is being

requested because BVPS–2 entered

Mode 5 for the purpose of performing its

fifth refueling outage on March 25,

1995, and upon completion of testing of

Recirculation Spray Pump 2RSS*P21A,

the licensee concluded that this pump

failed to satisfy the specific test

acceptance criteria in TS 4.6.2.2.d.

Pump disassembly for inspection and

repairs commenced on April 5, 1995.

The pump is scheduled to be

reassembled and flow tested by April

12, 1995. BVPS–2 is currently

scheduled to enter Mode 4 on May 4,

1995, at which time pump 2RSS*P21A

is required to be operable. If the pump

does not meet the specific test

acceptance criteria currently in TS

4.6.2.2d at that time, BVPS–2 will be

prohibited from entry into Mode 4. With

the proposed revision to TS 4.6.2.2.d,

the actual performance of pump

2RSS*P21A could then be evaluated

against accident analysis assumptions

and the pump’s acceptance criteria

could then be revised under the

provisions of 10 CFR 50.59 to establish

IST Program requirements that would

continue to maintain the plant within

the accident analysis assumptions. The

licensee could not have foreseen this

event since the pump’s performance

could not be tested until the plant

entered Mode 5 on March 25, 1995.

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.

Pursuant to 10 CFR 50.91(a)(6) for

amendments to be granted under

exigent circumstances, the NRC staff

must determine 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:

1. Does the change involve a significant

increase in the probability or consequences

of an accident previously evaluated?

The change does not result in a

modification to plant equipment nor does it

affect the manner in which the plant is

operated. The Recirculation Spray System

(RSS) pumps are normally in a standby

condition and only operate during accident

mitigation. Since the physical plant

equipment and operating practices are not

changed, as noted above, there is no change

in the probability of an accident previously

evaluated.

The proposed change will not lower the

pump performance operability criteria for the

RSS pumps. The required values for

developed pump head and flow will

continue to satisfy accident mitigation

requirements and will be maintained and

controlled in the Beaver Valley Power Station

(BVPS) Unit No. 2 Inservice Testing (IST)

Program.

Since the proposed change does not lower

the RSS pump performance acceptance

criteria, the containment depressurization

system will continue to meet its design basis

requirements. The proposed change will not

impose additional challenges to the

containment structure in terms of peak

pressure. The calculated offsite dose

consequences of a design basis accident

(DBA) will remain unchanged since the one

hour release duration remains unchanged.

The ability of the RSS pumps to provide

sufficient long term core cooling also remains

unchanged. The proposed change in the RSS

pump surveillance interval from 18 months