48680 Federal Register / Vol. 62, No. 179 / Tuesday, September 16, 1997 / Notices

Paragraph (c) of 10 CFR 70.24 exempts

Part 50 licensees from the requirements

of paragraph (b) of 10 CFR 70.24 for

SNM used or to be used in the reactor.

Paragraph (d) of 10 CFR 70.24 states that

any licensee who believes that there is

good cause why he should be granted an

exemption from all or part of 10 CFR

70.24 may apply to the Commission for

such an exemption and shall specify the

reasons for the relief requested.

III

The SNM that could be assembled

into a critical mass at Virgil C. Summer

Nuclear Station is in the form of nuclear

fuel; the quantity of SNM other than

fuel that is stored on site in any given

location is small enough to preclude

achieving a critical mass. The

Commission’s technical staff has

evaluated the possibility of an

inadvertent criticality of the nuclear fuel

at Virgil C. Summer Nuclear Station,

and has determined that it is extremely

unlikely that such an accident could

occur if the licensee meets the following

seven criteria:

1. Only one fuel assembly is allowed out

of a shipping cask or storage rack at one time.

2. The k-effective does not exceed 0.95, at

a 95% probability, 95% confidence level in

the event that the fresh fuel storage racks are

filled with fuel of the maximum permissible

U–235 enrichment and flooded with pure

water.

3. If optimum moderation occurs at low

moderator density, then the k-effective does

not exceed 0.98, at a 95% probability, 95%

confidence level in the event that the fresh

fuel storage racks are filled with fuel of the

maximum permissible U–235 enrichment

and flooded with a moderator at the density

corresponding to optimum moderation.

4. The k-effective does not exceed 0.95, at

a 95% probability, 95% confidence level in

the event that the spent fuel storage racks are

filled with fuel of the maximum permissible

U–235 enrichment and flooded with pure

water.

5. The quantity of forms of special nuclear

material, other than nuclear fuel, that are

stored on site in any given area is less than

the quantity necessary for a critical mass.

6. Radiation monitors, as required by

General Design Criterion 63, are provided in

fuel storage and handling areas to detect

excessive radiation levels and to initiate

appropriate safety actions.

7. The maximum nominal U–235

enrichment is limited to 5.0 weight percent.

By letter dated July 17, 1997, as

supplemented August 6, 1997, the

licensee requested an exemption from

10 CFR 70.24. In this request, the

licensee addressed the seven criteria

given above. The Commission’s

technical staff has reviewed the

licensee’s submittals and has

determined that Virgil C. Summer

Nuclear Station meets the criteria for

prevention of inadvertent criticality;

therefore, the staff has determined that

it is extremely unlikely for an

inadvertent criticality to occur in SNM

handling or storage areas at Virgil C.

Summer Nuclear Station.

The purpose of the criticality

monitors required by 10 CFR 70.24(a) is

to ensure that if a criticality were to

occur during the handling of SNM,

personnel would be alerted to that fact

and would take appropriate action. The

staff has determined that it is extremely

unlikely that such an accident could

occur; furthermore, the licensee has

radiation monitors, as required by

General Design Criterion 63, in fuel

storage and handling areas. These

monitors will alert personnel to

excessive radiation levels and allow

them to initiate appropriate safety

actions. The low probability of an

inadvertent criticality, together with the

licensee’s adherence to General Design

Criterion 63, constitutes good cause for

granting an exemption from the

requirements of 10 CFR 70.24.

IV

The Commission has determined that,

pursuant to 10 CFR 70.14, this

exemption is authorized by law, will not

endanger life or property or the common

defense and security, and is otherwise

in the public interest.

Therefore, the Commission hereby

grants the South Carolina Electric and

Gas Company an exemption from the

requirements of 10 CFR 70.24.

Pursuant to 10 CFR 51.32, the

Commission has determined that the

granting of this exemption will have no

significant impact on the environment

(62 FR 47521).

This exemption is effective upon

issuance.

Dated at Rockville, Maryland, this 9th day

of September 1997.

For the Nuclear Regulatory Commission.

Samuel J. Collins,

Director, Office of Nuclear Reactor

Regulation.

[FR Doc. 97–24559 Filed 9–15–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

Advisory Committee on Reactor

Safeguards Subcommittee Meeting on

Planning and Procedures

The ACRS Subcommittee on Planning

and Procedures will hold a meeting on

October 1, 1997, Room T–2B1, 11545

Rockville Pike, Rockville, Maryland.

The entire meeting will be open to

public attendance, with the exception of

a portion that may be closed pursuant

to 5 U.S.C. 552b(c) (2) and (6) to discuss

organizational and personnel matters

that relate solely to internal personnel

rules and practices of ACRS, and

information the release of which would

constitute a clearly unwarranted

invasion of personal privacy.

The agenda for the subject meeting

shall be as follows:

Wednesday, October 1, 1997–10:30 a.m.

Until 12:00 Noon

The Subcommittee will discuss

proposed ACRS activities and related

matters. It may also discuss the

qualifications of candidates for

appointment to the ACRS. 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 person named

below five days prior to the meeting, if

possible, so that appropriate

arrangements can be made.

Further information regarding topics

to be discussed, the scheduling of

sessions open to the public, 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 person, Dr.

John T. Larkins (telephone: 301/415–

7360) 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 changes in schedule, etc., that

may have occurred.

Dated: September 10, 1997.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 97–24556 Filed 9–15–97; 8:45 am]

BILLING CODE 7590–01–P