Federal Register / Vol. 63, No. 77 /Wednesday, April 22, 1998 / Notices 19963

Certificates of Compliance Nos. GDP–

1 and GDP–2: Amendments will revise

the Safety Analysis Reports based upon

the SARUP revisions.

Local Public Document Room

location: Paducah Public Library, 555

Washington Street, Paducah, Kentucky

42003 and Portsmouth Public Library,

1220 Gallia Street, Portsmouth, Ohio

45662.

Dated at Rockville, Maryland, this 13th day

of April 1998.

For the Nuclear Regulatory Commission.

Carl J. Paperiello,

Director, Office of Nuclear Material Safety

and Safeguards.

[FR Doc. 98–10667 Filed 4–21–98; 8:45 am]

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[Docket Nos. 50–413 and 50–414]

Duke Energy Corporation, et al.;

Catawba 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 amendments to

Facility Operating License Nos. NPF–35

and NPF–52, issued to Duke Energy

Corporation, et al. (the licensee), for

operation of the Catawba Nuclear

Station, Units 1 and 2, located in York

County, South Carolina.

Environmental Assessment

Identification of Proposed Action

The proposed action would amend

the Facility Operating Licenses (FOLs)

for Units 1 and 2 and to delete license

conditions that have been fulfilled,

delete exemptions that are no longer

needed, correct errors, and make other

administrative and editorial changes.

The proposed action is in response to

the licensee’s application dated

December 18, 1997, and revised by letter

dated January 26, 1998.

The Need for the Proposed Action

When the FOLs, NPF–35 and NPF–52,

were issued to the licensee, the NRC

staff deemed certain issues essential to

safety and/or essential to meeting

certain regulatory interests. These issues

were imposed as license conditions in

the FOLs, with deadlines for their

implementation. Since the units were

licensed to operate in the 1980s, most of

these license conditions have been

fulfilled. For the license conditions that

have been fulfilled, the licensee

proposed to have them deleted from the

FOLs.

The FOLs also included a number of

exemptions from NRC regulations. The

licensee stated that these exemptions

have either expired, or are no longer

needed since the units are in full

compliance with the respective

regulations. The licensee proposed to

delete these exemptions from the FOLs.

The licensee also proposed to make

changes to correct administrative errors

such as words inadvertently omitted,

documents erroneously cited, etc.

The proposed amendments involve

administrative changes to the FOLs

only. No actual plant equipment,

regulatory requirements, operating

practices, or analyses are affected by

these proposed amendments.

Environmental Impacts of the Proposed

Action

The Commission has completed its

evaluation of the proposed action and

concludes that there is no significant

environmental impact if the

amendments are granted. No changes

will be made to the design and licensing

bases, and applicable procedures at the

two units at Catawba Nuclear Station

will remain the same. Other than the

administrative changes, no other

changes will be made to the FOLs,

including the Technical Specifications.

The changes 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 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 related to the Catawba

Nuclear Station.

Agencies and Persons Contacted

In accordance with its stated policy,

on April 1, 1998, the staff consulted

with the South Carolina State official,

Virgil Autrey of the Bureau of

Radiological Health, South Carolina

Department of Health and

Environmental Control, regarding the

environmental impact of the proposed

amendments. The State official had no

comments.

Finding of No Significant Impact

Based upon the foregoing

environmental assessment, the

Commission concludes that the

proposed amendments 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

amendments.

For further details with respect to the

proposed action, see the licensee’s

request for the amendments dated

December 18, 1997, and revised by letter

dated January 26, 1998, 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

York County Library, 138 East Black

Street, Rock Hill, South Carolina.

Dated at Rockville, Maryland, this 15th day

of April 1998.

For the Nuclear Regulatory Commission.

Peter S. Tam,

Senior Project Manager, Project Directorate

II–2, Division of Reactor Projects—I/II, Office

of Nuclear Reactor Regulation.

[FR Doc. 98–10668 Filed 4–21–98; 8:45 am]

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Advisory Committee on Reactor

Safeguards Subcommittee Meeting on

Thermal-Hydraulic and SevereAccident Phenomena; Notice of

Meeting

The ACRS Subcommittee on ThermalHydraulic and Severe-Accident

Phenomena will hold a meeting on May

11 and 12, 1998, Room T–2B3, 11545

Rockville Pike, Rockville, Maryland.

Portions of the meeting will be closed

to public attendance to discuss
19964 Federal Register / Vol. 63, No. 77 /Wednesday, April 22, 1998 / Notices

Westinghouse Electric Company

proprietary information pursuant to 5

U.S.C. 552b(c)(4).

The agenda for the subject meeting

shall be as follows:

Monday, May 11, 1998—8:30 a.m.

until the conclusion of business.

Tuesday, May 12, 1998—8:30 a.m.

until the conclusion of business.

The Subcommittee will continue its

review of the results of the

Westinghouse Test and Analysis

Program supporting the AP600 design

certification. Specifically, the

Subcommittee will review issues

pertaining to the AP600 Reactor Coolant

System, including the resolution of

issues identified in the February 19,

1998 ACRS letter. The purpose of this

meeting is to gather information,

analyze relevant issues and facts, and to

formulate proposed positions and

actions, as appropriate, for deliberation

by the full Committee.

Oral statements may be presented by

members of the public with the

concurrence of the Subcommittee

Chairman; written statements will be

accepted and made available to the

Committee. Electronic recordings will

be permitted only during those portions

of the meeting that are open to the

public, and questions may be asked only

by members of the Subcommittee, its

consultants, and staff. Persons desiring

to make oral statements should notify

the cognizant ACRS staff engineer

named below five days prior to the

meeting, if possible, so that appropriate

arrangements can be made.

During the initial portion of the

meeting, the Subcommittee, along with

any of its consultants who may be

present, may exchange preliminary

views regarding matters to be

considered during the balance of the

meeting.

The Subcommittee will then hear

presentations by and hold discussions

with representatives of the

Westinghouse Electric Company, the

NRC staff, their consultants, and other

interested persons regarding this review.

Further information regarding topics

to be discussed, whether the meeting

has been canceled or rescheduled, the

scheduling of sessions which are open

to the public, the Chairman’s ruling on

requests for the opportunity to present

oral statements and the time allotted

therefor, can be obtained by contacting

the cognizant ACRS staff engineer, Mr.

Paul A. Boehnert (telephone 301/415–

8065) between 7:30 a.m. and 4:15 p.m.

(EDT). Persons planning to attend this

meeting are urged to contact the above

named individual one or two working

days prior to the meeting to be advised

of any potential changes to the agenda,

etc., that may have occurred.

Dated: April 16, 1998.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 98–10663 Filed 4–21–98; 8:45 am]

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COMMISSION

Advisory Committee on Reactor

Safeguards; Subcommittee Meeting on

Advanced Reactor Designs; Notice of

Meeting

The ACRS Subcommittee on

Advanced Reactor Designs will hold a

meeting on May 13–15, 1998, Room T–

2B3, 11545 Rockville Pike, Rockville,

Maryland.

The entire meeting will be open to

public attendance.

The agenda for the subject meeting

shall be as follows:

Wednesday, May 13, 1998—8:30 a.m.

until the conclusion of business.

Thursday, May 14, 1998—8:30 a.m.

until the conclusion of business.

Friday, May 15, 1998—8:30 a.m. until

the conclusion of business.

The Subcommittee will continue its

review of the Westinghouse AP600

design. Specifically, the Subcommittee

will review Chapters 3, 6, 9A, 14, 16,

and 17 of the AP600 Standard Safety

Analysis Report, the probabilistic risk

assessment (PRA), regulatory treatment

of non-safety systems (RTNSS), and the

associated NRC staff’s draft Final Safety

Evaluation Report. The purpose of this

meeting is to gather information,

analyze relevant issues and facts, and to

formulate proposed positions and

actions, as appropriate, for deliberation

by the full Committee.

Oral statements may be presented by

members of the public with the

concurrence of the Subcommittee

Chairman; written statements will be

accepted and made available to the

Committee. Electronic recordings will

be permitted only during those portions

of the meeting that are open to the

public, and questions may be asked only

by members of the Subcommittee, its

consultants, and staff. Persons desiring

to make oral statements should notify

the cognizant ACRS staff engineer

named below five days prior to the

meeting, if possible, so that appropriate

arrangements can be made.

During the initial portion of the

meeting, the Subcommittee, along with

any of its consultants who may be

present, may exchange preliminary

views regarding matters to be

considered during the balance of the

meeting.

The Subcommittee will then hear

presentations by and hold discussions

with representatives of the NRC staff,

Westinghouse Electric Company, their

consultants, and other interested

persons regarding this review.

Further information regarding topics

to be discussed, whether the meeting

has been canceled or rescheduled, and

the Chairman’s ruling on requests for

the opportunity to present oral

statements and the time allotted

therefor, can be obtained by contacting

the cognizant ACRS staff engineer, Mr.

Noel F. Dudley (telephone 301/415–

6888) between 7:30 a.m. and 4:15 p.m.

(EDT). Persons planning to attend this

meeting are urged to contact the above

named individual one or two working

days prior to the meeting to be advised

of any potential changes to the agenda,

etc., that may have occurred.

Dated: April 16, 1998.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 98–10664 Filed 4–21–98; 8:45 am]

BILLING CODE 7590–01–P

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Biweekly Notice; Applications and

Amendments to Facility Operating

Licenses Involving No Significant

Hazards Considerations

I. Background

Pursuant to Public Law 97–415, the

U.S. Nuclear Regulatory Commission

(the Commission or NRC staff) is

publishing this regular biweekly notice.

Public Law 97–415 revised section 189

of the Atomic Energy Act of 1954, as

amended (the Act), to require the

Commission to publish notice of any

amendments issued, or proposed to be

issued, under a new provision of section

189 of the Act. This provision grants the

Commission the authority to issue and

make immediately effective any

amendment to an operating license

upon a determination by the

Commission that such amendment

involves no significant hazards

consideration, notwithstanding the

pendency before the Commission of a

request for a hearing from any person.

This biweekly notice includes all

notices of amendments issued, or

proposed to be issued from March 30,

1998, through April 10, 1998. The last

biweekly notice was published on April

8, 1998 (63 FR 17219).