Federal Register / Vol. 62, No. 147 / Thursday, July 31, 1997 / Notices 41101

or radiological or chemical

consequences from, previously

evaluated accidents.

5. The proposed amendment will not

result in the possibility of a new or

different kind of accident.

The change will not create new

operating conditions or a new plant

configuration that could lead to a new

or different type of accident.

6. The proposed amendment will not

result in a significant reduction in any

margin of safety.

The proposed change corrects a

typographical error. As such, there is no

reductions in the margins of safety.

7. The proposed amendment will not

result in an overall decrease in the

effectiveness of the plant’s safety,

safeguards or security programs.

The proposed amendment corrects a

typographical error. As such, the

effectiveness of the safety, safeguards,

and security programs is not decreased.

Effective date: 30 days after issuance

Certificate of Compliance No. GDP–2:

Amendment will incorporate a revised

Surveillance Requirement of a

Technical Safety Requirement.

Local Public Document Room

location: Portsmouth Public Library,

1220 Gallia Street, Portsmouth, Ohio

45662.

Dated at Rockville, Maryland, this 22nd

day of July 1997.

For the Nuclear Regulatory Commission

Carl J. Paperiello,

Director Office of Nuclear Material Safety and

Safeguards.

[FR Doc. 97–20036 Filed 7–30–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket 70–7001]

Notice of Receipt of Amendment

Application to Certificate of

Compliance GDP–1 for The U.S.

Enrichment Corporation Paducah

Gaseous Diffusion Plant Paducah,

Kentucky; Notice of Comment Period

Notice is hereby given that the U.S.

Nuclear Regulatory Commission (NRC

or the Commission) has received an

amendment application from the United

States Enrichment Corporation that may

be considered to be significant pursuant

to 10 CFR 76.45. Any interested party

may submit written comments on the

application for amendment for

consideration by the staff. To be certain

of consideration, comments must be

received by September 2, 1997.

Comments received after the due date

will be considered if it is practical to do

so, but the Commission is able to assure

consideration only for comments

received on or before this date.

Written comments on the amendment

application should be mailed to the

Chief, Rules Review and Directives

Branch, Office of Administration, U.S.

Nuclear Regulatory Commission,

Washington, DC 20555, or may be hand

delivered to 11545 Rockville Pike,

Rockville, MD 20852 between 7:45 a.m.

and 4:15 p.m. Federal workdays.

Comments should be legible and

reproducible, and include the name,

affiliation (if any), and address of the

submitter. All comments received by the

Commission will be made available for

public inspection at the Commission’s

Public Document Room and the Local

Public Document Room. In accordance

with 10 CFR 76.62 and 76.64, a member

of the public must submit written

comments to be eligible to petition the

Commission requesting review of the

Director’s Decision on the amendment

request.

For further details with respect to the

action see the application for

amendment. The application 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.

Date of amendment request: April 23,

1997.

Brief description of amendment: The

amendment is related to the planned

modifications to upgrade the seismic

capability of Buildings C–331 and C–

335 at the Paducah Gaseous Diffusion

Plant. Specifically, the proposed

amendment will move back the

completion date for the seismic

modifications contained in Compliance

Plan Issue 36. Additionally, the

following three issues will be addressed:

(1) The increased stiffness of the

buildings following completion of the

modifications may increase the number

and the probability of seismicallyinduced equipment failures inside the

buildings; (2) the process of installing

the new structural steel may temporarily

make the building and contained

equipment more susceptible to

seismically-induced failure as the

existing structural frames are altered

and/or replaced; and (3) the process of

installing the new structural steel may

temporarily increase the probability of

equipment failures due to postulated

load handling accidents during

construction.

Certificate of Compliance No. GDP–1:

Amendment will revise Compliance

Plan Issue 36 on the seismic

modifications and will allow the

planned modifications to proceed.

Local Public Document Room

location: Paducah Public Library, 555

Washington Street, Paducah, Kentucky

42003.

Dated at Rockville, Maryland, this 22nd

day of July 1997.

For the Nuclear Regulatory Commission.

Carl J. Paperiello,

Director, Office of Nuclear Material Safety

and Safeguards.

[FR Doc. 97–20039 Filed 7–30–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket Nos. 50–369 and 50–370]

Duke Power Company; McGuire

Nuclear Station, Units 1 and 2;

Environmental Assessment and;

Finding of No Significant Impact

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an exemption

from certain requirements of its

regulations for Facility Operating

License Nos. NPF–9 and NPF–17 issued

to the Duke Power Company (the

licensee), for operation of the McGuire

Nuclear Station, Units 1 and 2, located

in Mecklenburg County, North Carolina.

Environmental Assessment

Identification of Proposed Action

The proposed action would exempt

the licensee from the requirements of 10

CFR 70.24, which requires a monitoring

system that will energize clear audible

alarms if accidental criticality occurs in

each area in which special nuclear

material is handled, used, or stored. The

proposed action would also exempt the

licensee from the requirements to

maintain emergency procedures for each

area in which this licensed special

nuclear material is handled, used, or

stored to ensure that all personnel

withdraw to an area of safety upon the

sounding of the alarm, to familiarize

personnel with the evacuation plan, and

to designate responsible individuals for

determining the cause of the alarm, and

to place radiation survey instruments in

accessible locations.

The proposed action is in response to

the licensee’s application dated

February 4, 1997, as supplemented on

March 19, 1997.

The Need for the Proposed Action

The purpose of 10 CFR 70.24 is to

ensure that if a criticality were to occur

during the handling of special nuclear

material, personnel would be alerted to

that fact and would take appropriate

action. At a commercial nuclear power