Federal Register / Vol. 62, No. 31 / Friday, February 14, 1997 / Notices 7077

the requested actions were to be

required. A copy of this evaluation will

be made available in the NRC Public

Document Room.

Dated at Rockville, Maryland, this 10th day

of February 1997.

For the Nuclear Regulatory Commission.

Thomas T. Martin,

Director, Division of Reactor Program

Management, Office of Nuclear Reactor

Regulation.

[FR Doc. 97–3737 Filed 2–13–97; 8:45 am]

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Advisory Committee on Reactor

Safeguards Joint Meeting of the ACRS

Subcommittees on Materials and

Metallurgy and on Severe Accidents;

Meeting

The ACRS Subcommittees on

Materials and Metallurgy and on Severe

Accidents will hold a joint meeting on

March 4 and 5, 1997, 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:

Tuesday, March 4, 1997—8:30 a.m.

until the conclusion of business

Wednesday, March 5, 1997—8:30 a.m.

until 12:00 Noon

The Subcommittees will review the

regulatory analysis and technical bases

for the steam generator tube integrity

rule, as well as an associated regulatory

guide. 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 Subcommittees, their

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 Subcommittees, along with

any of their consultants who may be

present, may exchange preliminary

views regarding matters to be

considered during the balance of the

meeting.

The Subcommittees will then hear

presentations by and hold discussions

with representatives of the NRC staff

and other interested persons regarding

this review.

Further information regarding topics

to be discussed, whether the meeting

has been cancelled or rescheduled, 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. (ET). 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: February 7, 1997.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 97–3738 Filed 2–13–97; 8:45 am]

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[DD–97–03]

Director’s Decision Under 10 CFR

2.206

In the Matter of Davis-Besse Nuclear Power

Station and Toledo Coalition for Safe

Energy.

Notice is hereby given that the

Director, Office of Nuclear Material

Safety and Safeguards, has taken action

with regard to the Petition of December

5, 1995, by the Toledo Coalition for Safe

Energy, Alice Hirt, Charlene Johnston,

Dini Schut, and William Hoops

(Petitioners), that the Director of the

Office of Nuclear Material Safety and

Safeguards exercise his authority to

immediately issue orders to prevent the

loading of spent nuclear fuel into the

VECTRA Technologies, Inc. (VECTRA)

NUHOMS dry-shielded canisters (DSCs)

at the Davis-Besse Nuclear Power

Station until an NRC rulemaking and/or

license modification hearing is

conducted on all safety-related changes

which have been made to the DSCs, as

described in the Safety Analysis Report.

Also, the NRC was requested not to

authorize any loading of the DSCs until

a written procedure for unloading, in

both urgent and non-urgent

circumstances, was written, approved,

and field-tested.

Petitioners contend that the safety of

the DSCs has been compromised

because of reduction in the thickness of

the DSC welds. In addition, they claim

that the NRC administrative process by

which permission was granted for

VECTRA to deliver the DSCs to the

Davis-Besse station and for the DSCs to

be used on site are legally suspect,

expressing the belief that agency

rulemaking or some other public

proceeding is necessary for permission

for such a transfer and use to be granted.

The Director of the Office of Nuclear

Material Safety and Safeguards has

determined that the NRC Certificate of

Compliance for VECTRA’s standardized

NUHOMS should be modified to require

a fabrication inspection of the DSC. An

agency rulemaking is, therefore, needed

and should be conducted to accomplish

this modification. However, because the

continued storage of spent fuel in the

DSCs at Davis-Besse does not pose an

unreasonable risk to public health and

safety, there is no technical basis to

require the DSCs to be unloaded

pending completion of this rulemaking.

Further, VECTRA has already been cited

for a nonconformance with NRC

regulations, and there is no basis in the

Petition to take other action in this

regard. Toledo Edison has developed

loading and unloading procedures for

handling spent fuels. These procedures

have been applied for the dry run

testing with NRC’s oversight. Therefore,

there is no basis in the Petition for

requiring halting of the ISFSI operation

at Davis-Besse. Accordingly, the Petition

from the Toledo Coalition for Safe

Energy is granted to the extent that it

requests an agency rulemaking and is

denied in all other respects. The reasons

for this decision are explained in the

‘‘Director’s Decision under 10 CFR

2.206’’ (DD–97–03), which is available

for public inspection in the

Commission’s Public Document Room,

Gelman Building, 2120 L Street, NW,

Washington, DC 20555, and in the Local

Public Document Room, William

Carlson Library, University of Toledo,

2001 West Bancroft Avenue, Toledo,

Ohio 43606.

A copy of this Decision will be filed

with the Office of the Secretary for the

Commission in accordance with 10 CFR

2.206(c). As provided by this regulation,

the Decision will constitute the final

action of the Commission 25 days after

the date of issuance of the Decision

unless the Commission, on its own

motion, institutes a review of the

Decision within that time.

Dated at Rockville, Maryland, this 5th day

of February 1997.

For the Nuclear Regulatory Commission.

Carl J. Paperiello,

Director, Office of Nuclear Material Safety

and Safeguards.

[FR Doc. 97–3739 Filed 2–13–97; 8:45 am]

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