34882 Federal Register / Vol. 61, No. 129 / Wednesday, July 3, 1996 / Notices

the applicant on a material issue of law

or fact. Contentions shall be limited to

matters within the scope of the

amendment under consideration. The

contention must be one which, if

proven, would entitle the petitioner to

relief. A petitioner who fails to file such

a supplement which satisfies these

requirements with respect to at least one

contention will not be permitted to

participate as a party.

Those permitted to intervene become

parties to the proceeding, subject to any

limitations in the order granting leave to

intervene, and have the opportunity to

participate fully in the conduct of the

hearing, including the opportunity to

present evidence and cross-examine

witnesses.

If the amendment is issued before the

expiration of the 30-day hearing period,

the Commission will make a final

determination on the issue of no

significant hazards consideration. If a

hearing is requested, the final

determination will serve to decide when

the hearing is held.

If the final determination is that the

amendment request involves no

significant hazards consideration, the

Commission may issue the amendment

and make it immediately effective,

notwithstanding the request for a

hearing. Any hearing held would take

place after issuance of the amendment.

If the final determination is that the

amendment request involves a

significant hazards consideration, any

hearing held would take place before

the issuance of any amendment.

A request for a hearing or a petition

for leave to intervene must be filed with

the Secretary of the Commission, U.S.

Nuclear Regulatory Commission,

Washington, DC 20555–0001, Attention:

Docketing and Services Branch, or may

be delivered to the Commission’s Public

Document Room, the Gelman Building,

2120 L Street, NW., Washington, DC, by

the above date. Where petitions are filed

during the last 10 days of the notice

period, it is requested that the petitioner

promptly so inform the Commission by

a toll-free telephone call to Western

Union at 1 (800) 248–5100 (in Missouri

1 (800) 342–6700). The Western Union

operator should be given Datagram

Identification Number N1023 and the

following message addressed to Herbert

N. Berkow: petitioner’s name and

telephone number, date petition was

mailed, plant name, and publication

date and page number of this Federal

Register notice. A copy of the petition

should also be sent to the Office of the

General Counsel, U.S. Nuclear

Regulatory Commission, Washington,

DC 20555–0001, and to M. Stanford

Blanton, Esq., Balch and Bingham, P.O.

Box 306, 1710 Sixth Avenue,

Birmingham, Alabama, attorney for the

licensee.

Nontimely filings of petitions for

leave to intervene, amended petitions,

supplemental petitions and/or requests

for hearing will not be entertained

absent a determination by the

Commission, the presiding officer or the

presiding Atomic Safety and Licensing

Board that the petition and/or request

should be granted based upon a

balancing of the factors specified in 10

CFR 2.714(a)(1)(i)–(v) and 2.714(d).

For further details with respect to this

action, see the application for

amendment dated June 24, 1996, 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

Houston-Love Memorial Library, 212 W.

Burdeshaw Street, P.O. Box 1369,

Dothan, Alabama.

Dated at Rockville, Maryland, this 27th day

of June 1996.

For the Nuclear Regulatory Commission.

Byron L. Siegel,

Project Manager, Project Directorate II–2,

Division of Reactor Projects—I/II, Office of

Nuclear Reactor Regulation.

[FR Doc. 96–16964 Filed 7–2–96; 8:45 am]

BILLING CODE 7590–01–P

Boraflex Degradation in Spent Fuel

Pool Storage Racks; Issued

AGENCY: Nuclear Regulatory

Commission.

ACTION: Notice of Issuance.

SUMMARY: The Nuclear Regulatory

Commission (NRC) has issued Generic

Letter 96–04 to notify all licensees of

nuclear power reactors about problems

that have been encountered with using

Boraflex in spent fuel storage racks for

the nonproductive absorption of

neutrons, and for licensees that use

Boraflex, to request implementation of

certain actions and require the submittal

of a written response. This generic letter

is available in the NRC Public

Document Room under accession

number 9606240132.

DATES: The generic letter was issued on

June 26, 1996.

ADDRESSEES: Not applicable.

FOR FURTHER INFORMATION CONTACT:

Laurence I. Kopp at (301) 415–2879.

SUPPLEMENTARY INFORMATION: The

information that is being requested will

enable the NRC staff to determine

whether licensees are complying with

the current licensing basis for the

facility with respect to GDC 62 for the

prevention of criticality in fuel storage

and handling, and 5-percent

subcriticality margins that are either

contained in the technical

specifications, or committed to in the

updated FSARs, of plants containing

Boraflex in the spent fuel storage racks.

The staff is not establishing a new

position for such compliance in this

generic letter.

Dated at Rockville, Maryland, this 26th day

of June, 1996.

For the Nuclear Regulatory Commission.

Elinor G. Adensam,

Deputy Director, Division of Reactor Program

Management, Office of Nuclear Reactor

Regulation.

[FR Doc. 96–16963 Filed 7–2–96; 8:45 am]

BILLING CODE 7590–01–P

Advisory Committee on Reactor

Safeguards; Meeting Notice

In accodance with the purposes of

Sections 29 and 182b. of the Atomic

Energy Act (42 U.S.C. 2039, 2232b), the

Advisory Committee on Rector

Safeguards will hold a meeting on

August 8–10, 1996, in Conference Room

T–2B3, 11545 Rockville Pike, Rockville,

Maryland. The date of this meeting was

previously published in the Federal

Register on Monday, November 27,

1995 (60 FR 58393).

Thursday, August 8, 1996

8:30 A.M.–8:45 A.M.: Opening Remarks

by the ACRS Chairman

(Open)—The ACRS Chairman will

make opening remarks regarding

conduct on the meeting and comment

briefly regarding items of current

interest. During this session, the

Committee will discuss priorities for

preparation of ACRS reports.

8:45 A.M.–10:45 A.M.: Supplemental

Safety Evaluation Report for

Evolutionary Plant Designs

(Open/Closed)—The Committee will

hear presentations by and hold

discussions with representatives of the

NRC staff, General Electric Nuclear

Energy (GENE), and ABB-Combustion

Engineering (ABB–CE) regarding the

proposed changes to the GENE

Advanced Boiling Water Reactor

(ABWR) and ABB–CE System 80+

evolutionary plant designs and the

associated NRC staff Safety Evaluation

Report. Other interested parties will

participate, as appropriate.

A portion of this session may be

closed to discuss GENE and ABB–CE

proprietary information applicable to

this matter.