20840 Federal Register / Vol. 61, No. 90 / Wednesday, May 8, 1996 / Notices

PLACE: Board Conference Room,

Eleventh Floor, 1099 Fourteenth St.,

N.W., Washington, D.C. 20570.

STATUS: Closed to public observation

pursuant to 5 U.S.C. Section 552b(c)(2)

(internal personnel rules and practices);

and 9(B) (disclosure would significantly

frustrate implementation of a proposed

Agency * * * ).

MATTERS TO BE CONSIDERED: Budget.

CONTACT PERSON FOR MORE INFORMATION:

John J. Toner, Executive Secretary,

Washington, D.C. 20570, Telephone:

(202) 273–1940.

Dated: Washington, D.C., May 2, 1996.

By direction of the Board:

John J. Toner,

Executive Secretary, National Labor Relations

Board.

[FR Doc. 96–11617 Filed 5–6–96; 2:01 pm]

BILLING CODE 7545–01–M

NUCLEAR REGULATORY

COMMISSION

[Docket No. 50–440]

Cleveland Electric Illuminating and

Ohio Edison Company, et al.; Notice of

Transfer of Ownership of Perry Nuclear

Power Plant

Notice is hereby given that the United

States Nuclear Regulatory Commission

(Commission) is considering approval

under Title 10 of the Code of Federal

Regulations (CFR), Section 50.80, of the

transfer of 12.58-percent ownership of

the facilities for the Perry Nuclear

Power Plant, Unit No. 1 (PNPP Unit 1)

from the Ohio Edison Company (Ohio

Edison) to a wholly owned subsidiary of

Ohio Edison, OES Nuclear, Inc. (OES).

By ‘‘Supplemental Application For

License Transfer,’’ submitted under

cover of letter dated December 29, 1995,

from Shaw, Pittman, Potts and

Trowbridge, Ohio Edison informed the

Commission that it intends to transfer to

OES a 12.58-percent ownership interest

in the PNPP Unit 1 ‘‘common facilities.’’

This request supplements an earlier

request to transfer a 17.42-percent

ownership interest in PNPP Unit 1 from

Ohio Edison to OES, which the NRC

approved by Order dated December 20,

1995. Further, OES has been added to

Operating License No. NPF–58 as an

owner of PNPP Unit 1, by Amendment

No. 81, dated February 27, 1996.

Pursuant to 10 CFR 50.80, the

Commission may approve the transfer of

a license, after notice to interested

persons, upon the Commission’s

determination that the holder of the

license following the transfer of control

is qualified to be a holder of the license

and the transfer of the control is

otherwise consistent with applicable

provisions of law, regulations and

orders of the Commission. Ohio Edison

has requested consent under 10 CFR

50.80 to transfer of the license

effectuated by the change in control of

such ownership interest in PNPP Unit 1.

For further details with respect to this

action, see the December 29, 1995, letter

and accompanying submittal, 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

Perry Public Library, 3753 Main Street,

Perry, Ohio.

Dated at Rockville, Maryland this 2nd day

of May 1996.

For the Nuclear Regulatory Commission.

Gail H. Marcus,

Director, Project Directorate III–3, Division

of Reactor Projects—III/IV, Office of Nuclear

Reactor Regulation.

[FR Doc. 96–11430 Filed 5–07–96; 8:45 am]

BILLING CODE 7590–01–P

[Docket Nos. 50–352 and 50–353]

Philadelphia Electric 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 Licenses Nos.

NPF–39 and NPF–85 issued to

Philadelphia Electric Company (the

licensee) for operation of the Limerick

Generating Station (LGS), Units 1 and 2,

located in Montgomery County,

Pennsylvania.

The proposed amendment would

relocate the Technical Specifications

(TSs) Traversing In-Core Probe (TIP)

System Limiting Condition For

Operation (LCO) 3/4.3.7.7, and its Bases

3/4.3.7.7, to LGS Technical

Requirements Manual (TRM) and

modify Note (f) of TS Table 4.3.1.1–1,

‘‘Reactor Protection System

Instrumentation Surveillance

Requirements,’’ to remove its reference

to the TIP System in accordance with

NRC NUREG–1433, ‘‘Standard

Technical Specifications, General

Electric Plants, BWR/4.’’

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:

1. The proposed TS changes do not involve

a significant increase in the probability or

consequences of an accident previously

evaluated.

The proposed changes will relocate

requirements from TS to a licensee controlled

document (i.e., TRM) and delete surveillance

details pertaining to the TIP system which

are already contained in licensee controlled

documents. The relocated requirements will

be retained in licensee controlled documents

which will be maintained under the

requirements of TS Administrative Controls

Section 6.0 and the provisions of 10 CFR

50.59. Since any changes to licensee

controlled documents are required to be

evaluated per 10 CFR 50.59, no increase

(significant or insignificant) in the

probability or consequences of an accident

previously evaluated will be allowed.

In addition, these proposed changes will

not affect any equipment important to safety,

in structure or operation. These changes will

not alter operation of process variables,

structures, systems, or components as

described in the safety analysis report and

licensing basis. The changes will not increase

the probability or consequences of

occurrence of a malfunction of equipment

important to safety previously evaluated in

the SAR [Safety Analysis Report].

2. The proposed TS changes do not create

the possibility of a new or different kind of

accident from any accident previously

evaluated.

The proposed changes will not alter the

plant configuration or change the methods

governing normal plant operation. The

changes will not impose different operating

requirements and adequate control of

information will be retained. The changes

will not alter assumptions made in the safety

analysis report and licensing basis. Since the

proposed changes cannot cause an accident,

and the plant response to the design basis

events is unchanged, the changes do not

create the possibility of a new or different

kind of accident from any accident

previously evaluated.

3. The proposed TS changes do not involve

a significant reduction in a margin of safety.

The proposed changes to relocate

requirements from TS to a licensee controlled

document and modify surveillance details

pertaining to the TIP system which are