59216 Federal Register / Vol. 65, No. 193 / Wednesday, October 4, 2000 / Notices

must be accompanied or preceded by an

LTP to be submitted for NRC approval.

If found acceptable by the NRC staff, the

LTP is approved by license amendment,

subject to such conditions and

limitations as the NRC staff deems

appropriate and necessary. CYAPC

submitted the proposed LTP for HNP by

application dated July 7, 2000. In

accordance with 10 CFR 20.1405 and 10

CFR 50.82(a)(9)(iii), the NRC provided

notice to individuals in the vicinity of

the site that the NRC was in receipt of

the HNP LTP and would accept

comments from affected parties (65 FR

51345). In accordance with 10 CFR

50.82(a)(9)(iii), the NRC is hereby

providing notice that NRC staff will

conduct a meeting to discuss the HNP

LTP.

The HNP LTP (ADAMS Accession

Number ML003735143) may be

examined, and/or copied for a fee, at the

NRC’s Public Document Room, located

at One White Flint North, 11555

Rockville Pike (first floor), Rockville,

Maryland, and is accessible

electronically from the ADAMS Public

Library component on the NRC Web

site, http://www.nrc.gov (the Public

Electronic Reading Room). The LTP may

also be viewed at the CYAPC Web site

at www.connyankee.com.

For further information, contact: Mr.

Louis L. Wheeler by mail, Mail Stop O–

7–C2, Project Directorate IV &

Decommissioning, Division of Licensing

Project Management, Office of Nuclear

Reactor Regulation, U.S. Nuclear

Regulatory Commission, Washington,

D.C. 20555–0001; telephone 301–415–

1444; or e-mail dxw@nrc.gov.

Dated at Rockville, Maryland, this 28th day

of September 2000.

For the Nuclear Regulatory Commission.

Michael T. Masnik,

Chief, Decommissioning Section, Project

Directorate IV and Decommissioning,

Division of Licensing Project Management,

Office of Nuclear Reactor Regulation.

[FR Doc. 00–25462 Filed 10–3–00; 8:45 am]

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[Docket No. 50–368]

Entergy Operations, Inc.; Arkansas

Nuclear One, Unit 2 Environmental

Assessment and Finding of No

Significant Impact

The U.S. Nuclear Regulatory

Commission (NRC) is considering

issuance of an exemption from 10 CFR

Part 50, Appendix J, for Facility

Operating License No. NPF–6, issued to

Entergy Operations, Inc. (the licensee),

for operation of Arkansas Nuclear One,

Unit 2 (ANO–2), located in Pope

County, Arkansas.

Environmental Assessment

Identification of the Proposed Action

The proposed action would provide a

one-time exemption to Entergy

Operations, Inc. from the requirements

of Title 10 of the Code of Federal

Regulations (10 CFR) Part 50, Appendix

J, ‘‘Primary Reactor Containment

Leakage Testing For Water-Cooled

Power Reactors,’’ which requires that

licensees of all power reactors conduct

integrated leakage rate tests (ILRT)

under conditions representing design

basis loss-of-coolant accident

containment peak pressure. The

licensee requires an exemption in order

to conduct the ILRT at the same

pressure that is used for the structural

integrity test (SIT).

The proposed action is in accordance

with the licensee’s application for

exemption dated June 29, 2000.

The Need for the Proposed Action

The ANO–2 steam generators (SGs)

are scheduled for replacement during

the fall of 2000. The replacement SGs

(RSGs) will require that an access

opening be cut in the containment

building structure. Upon closure of the

structure, an ILRT will be required to

test for primary containment leakage

integrity.

The ANO–2 containment building

was originally designed and tested for

an internal pressure of 54 psig. The

ANO–2 containment building has

recently been reevaluated, to address

the containment post-accident response

resulting from the RSGs, for an increase

in accident pressure to 58 psig with a

design pressure of 59 psig, and shown

to be acceptable as discussed in a letter

to the NRC dated November 3, 1999, as

revised by a letter dated June 29, 2000.

As a result of this increase, an SIT will

be performed to evaluate the ANO–2

containment building for the change in

containment design pressure. The

purpose of the SIT is to verify that the

containment building structure can

safely carry design loads and that the

structural behavior is similar to that

predicted by analysis. The post-RSG SIT

will be performed at 68 psig (1.15 times

the revised design pressure). The

licensee would like to also perform the

ILRT concurrently with the post-RSG

SIT, at the SIT pressure of 68 psig, in

order to recover approximately 30 hours

of projected plant outage time. However,

Appendix J requires that the ILRT be

conducted at a pressure representing the

design basis loss-of-coolant accident

containment peak pressure, which is 58

psig. Hence, the need for the proposed

exemption.

Environmental Impacts of the Proposed

Action

The NRC has completed its evaluation

of the proposed action and concludes

that the proposed action will not

significantly increase the probability or

consequences of accidents, no changes

are being made in the types of any

effluents that may be released off site,

and there is no significant increase in

occupational or public radiation

exposure. Therefore, there are no

significant radiological environmental

impacts associated with the proposed

action.

With regard to potential

nonradiological impacts, the proposed

action does not involve any historic

sites. It does not affect nonradiological

plant effluents and has no other

environmental impact. Therefore, there

are no significant nonradiological

environmental impacts associated with

the proposed action.

Accordingly, the NRC concludes that

there are no significant environmental

impacts associated with the proposed

action.

Alternatives to the Proposed Action

As an alternative to the proposed

action, the staff considered denial of the

proposed action (i.e., the ‘‘no-action’’

alternative). 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 Operation of

Arkansas Nuclear One, Unit 2,’’ dated

June 1977.

Agencies and Persons Consulted

In accordance with its stated policy,

on September 7, 2000, the staff

consulted with the Arkansas State

official, Bernie Bevill of the Arkansas

Department of Health, regarding the

environmental impact of the proposed

action. The State official had no

comments.

Finding of No Significant Impact

On the basis of the environmental

assessment, the NRC concludes that the

proposed action will not have a

significant effect on the quality of the

human environment. Accordingly, the

Federal Register / Vol. 65, No. 193 / Wednesday, October 4, 2000 / Notices 59217

NRC has determined not to prepare an

environmental impact statement for the

proposed action.

For further details with respect to the

proposed action, see the licensee’s letter

dated June 29, 2000, which may be

examined, and/or copied for a fee, at the

NRC’s Public Document Room, located

at One White Flint North, 11555

Rockville Pike (first floor), Rockville,

Maryland. Publicly available records

will be accessible electronically from

the ADAMS Public Library component

on the NRC Web site, http:www.nrcgov

(the Electronic Reading Room).

Dated at Rockville, Maryland, this 28th day

of September 2000.

For the Nuclear Regulatory Commission.

Mohan C. Thadani,

Acting Chief, Section 1, Project Directorate

IV–1 & Decommissioning Division of

Licensing Project Management, Office of

Nuclear Reactor Regulation.

[FR Doc. 00–25463 Filed 10–3–00; 8:45 am]

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Advisory Committee on Reactor

Safeguards; Meeting of the Ad Hoc

Subcommittee; Revised

The ACRS Ad Hoc Subcommittee

meeting scheduled for October 10–13,

2000 has been extended to Saturday,

October 14, 2000, Room T–2B3, 11545

Rockville Pike, Rockville, Maryland,

8:30 a.m. until 12 Noon to discuss

proposed comments and

recommendations on the technical

merits of the Differing Professional

Opinion Issues associated with steam

generator tube integrity. Notice of this

meeting was previously published in

the Federal Register on Wednesday,

September 20, 2000 (65 FR 56945). All

other items pertaining to this meeting

remains the same as previously

published.

For further information contact either

Mr. Sam Duraiswamy (telephone 301–

415–7364) or Ms. Undine Shoop

(telephone 301–415–8086) between 7:30

a.m. and 4:15 p.m. (EDT).

Dated: September 28, 2000.

James E. Lyons,

Associate Director for Technical Support,

ACRS/ACNW.

[FR Doc. 00–25459 Filed 10–3–00; 8:45 am]

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Advisory Committee on Reactor

Safeguards; Meeting of the

Subcommittee on Plant License

Renewal

The ACRS Subcommittee on Plant

License Renewal will hold a meeting on

October 19–20, 2000, Room T–2B1,

11545 Rockville Pike, Rockville,

Maryland.

The entire meeting will be open to

public attendance.

The agenda for the subject meeting

shall be as follows:

Thursday, October 19, 2000—8 a.m.

until the conclusion of business.

The Subcommittee will review drafts

of the Standard Review Plan for license

renewal and the Generic Aging Lessons

Learned (GALL) Report sections 2, 3,

and 4.

Friday, October 20, 2000—8 a.m. until

the conclusion of business.

The Subcommittee will review drafts

of GALL Report sections 5 through 8,

the associated Regulatory Guide, and

Nuclear Energy Institute (NEI) 95–10,

‘‘Industry Guideline For Implementing

The Requirements of 10 CFR Part 54—

The License Renewal Rule.’’

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,

the Nuclear Energy Institute, 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: September 28, 2000

James E. Lyons,

Associate Director for Technical Support,

ACRS/ACNW.

[FR Doc. 00–25460 Filed 10–3–00; 8:45 am]

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Advisory Committee on Reactor

Safeguards; Subcommittee Meeting on

Reactor Fuels; Notice of Meeting

The ACRS Subcommittee on Reactor

Fuels will hold a meeting on October

18, 2000, Room T–2B1, 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, October 18, 2000—8:30

a.m. until the conclusion of business.

The Subcommittee will discuss the

status of the staff’s effort regarding the

draft report of a technical study of Spent

Fuel Pool Accident Risk at

Decommissioning Nuclear Power Plants,

and related matters. 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