Federal Register / Vol. 62, No. 178 / Monday, September 15, 1997 / Notices 48321

specifically explain the reasons why

review of the Decision should be

permitted with particular reference to

the following factors: (1) The interest of

the petitioner; (2) how that interest may

be affected by the Decision, including

the reasons why the petitioner should

be permitted a review of the Decision;

and (3) the petitioner’s areas of concern

about the activity that is the subject

matter of the Decision. Any person

described in this paragraph (USEC or

any person who filed a petition) may

file a response to any petition for

review, not to exceed 30 pages, within

10 days after filing of the petition. If no

petition is received within the

designated 15-day period, the Director

will issue the final amendment to the

Certificate of Compliance without

further delay. If a petition for review is

received, the decision on the

amendment application will become

final in 60 days, unless the Commission

grants the petition for review or

otherwise acts within 60 days after

publication of this Federal Register

notice.

A petition for review must be filed

with the Secretary, U.S. Nuclear

Regulatory Commission, Washington,

DC 20555–0001, Attention: Rulemakings

and Adjudications Staff, or may be

delivered to the Commission’s Public

Document Room, the Gelman Building,

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

the above date.

For further details with respect to the

action see (1) the application for

amendment and (2) the Commission’s

Compliance Evaluation Report. These

items 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.

Date of amendment request: June 16,

1997.

Brief description of amendment: The

amendment proposes to revise the

Technical Safety Requirement (TSR) for

the Nuclear Criticality Safety Program

by adding a new program element.

Basis for Finding of No Significance

1. The proposed amendment will not

result in a change in the types or

significant increase in the amounts of

any effluents that may be released

offsite.

The proposed change involves

revision of the Nuclear Criticality Safety

Program TSR to add a new program

element on identification of safety

structures, systems and components

(SSCs) required to meet the double

contingency. Because there are no

effluent release associated with this

change, the proposed changes will not

affect the effluent.

2. The proposed amendment will not

result in a significant increase in

individual or cumulative occupational

radiation exposure.

The proposed changes do not relate to

controls used to minimize occupational

radiation exposures, therefore, the

changes will not increase exposure.

3. The proposed amendment will not

result in a significant construction

impact.

The proposed changes will not result

in any construction, therefore, there will

be no construction impacts.

4. The proposed amendment will not

result in a significant increase in the

potential for, or radiological or chemical

consequences from, previously analyzed

accidents.

The proposed changes will not

increase the probability of occurrence or

consequence of any postulated accident

currently identified in the safety

analysis report. Therefore, there is no

significant increase in the potential for

or radiological or chemical

consequences from previously evaluated

accidents.

5. The proposed amendment will not

result in the possibility of a new or

different kind of accident.

Changing the TSR to add a new

program element will not create a new

or different type of accident. The

proposed changes would not create new

operating conditions or new plant

configuration that could lead to a new

or different type of accident.

6. The proposed amendment will not

result in a significant reduction in any

margin of safety.

There are no increases in the

probability or consequences of a

criticality and no new accident

initiators were identified. These changes

do not increase the margins of safety. In

fact safety may be enhanced by putting

more emphasis on the clear

identification of SSCs necessary to meet

the double contingency principle.

7. The proposed amendment will not

result in an overall decrease in the

effectiveness of the plant’s safety,

safeguards or security programs.

Implementation of the proposed

changes do not change the safety,

safeguards, or security programs.

Although the program element is being

added to the TSR, there was already a

commitment to identify the SSCs. The

effectiveness of the safety, safeguards,

and security programs is not decreased.

Effective date: The amendment to

Certificate of Compliance GDP–1

becomes effective 30 days after being

signed by the Director, Office of Nuclear

Material Safety and Safeguards.

Certificate of Compliance No. GDP–1:

Amendment will revise Technical

Safety Requirement for the nuclear

criticality safety program by adding a

new program element.

Local Public Document Room

location: Paducah Public Library, 555

Washington Street, Paducah, Kentucky

42003.

Dated at Rockville, Maryland, this 2nd day

of September 1997.

For the Nuclear Regulatory Commission.

William F. Kane,

Acting Deputy Director, Office of Nuclear

Material Safety and Safeguards.

[FR Doc. 97–24384 Filed 9–12–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

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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

September 29–30, 1997, Room T–2B3,

11545 Rockville Pike, Rockville,

Maryland.

Most of the meeting will be closed to

public attendance to discuss

Westinghouse Electric Corporation

proprietary information pursuant to 5

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

The agenda for the subject meeting

shall be as follows:

Monday, September 29, 1997—8:30

a.m. until the conclusion of business

Tuesday, September 30, 1997—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 being conducted in support of

the AP600 design certification and the

associated NRC staff’s Supplemental

Draft Safety Evaluation Report.

Specifically, the Subcommittee will

review key elements of the passive

containment cooling system test and

analysis program. 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
48322 Federal Register / Vol. 62, No. 178 / Monday, September 15, 1997 / Notices

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 Corporation, the

NRC staff, their consultants, and other

interested persons regarding this review.

Further information regarding topics

to be discussed, whether the meeting

has been cancelled 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: September 9, 1997.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 97–24376 Filed 9–12–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

Sunshine Act Meeting

AGENCY HOLDING THE MEETING: Nuclear

Regulatory Commission.

DATE: Week of September 15.

PLACE: Commissioners’ Conference

Room, 11555 Rockville Pike, Rockville,

Maryland.

STATUS: Public and Closed.

MATTERS TO BE CONSIDERED:

Week of September 15

Wednesday, September 17

9:00 a.m.—Briefing by DOE on

Plutonium Disposition Strategy and

Program (Public Meeting) (Contact:

Ted Sherr, 301–415–7218)

Friday, September 19

10:00 a.m.—Briefing by DOE and NRC

on Regulatory Oversight of DOE

Nuclear Facilities (Public Meeting)

(Contact: John Austin, 301–415–7275)

11:30 a.m.—Affirmation Session (Public

Meeting) (if needed)

1:30 p.m.—Briefing on Improvements in

Senior Management Assessment

Process for Operating Reactors (Public

Meeting) (Contact: Bill Borchardt,

301–415–1257)

* * * *

*The Schedule for Commission

Meetings is Subject to Change on Short

Notice. To Verify the Status of Meetings

Call (Recording)—(301) 415–1292.

Contact Person for More Information:

Bill Hill, (301) 415–1661.

* * * * *

The NRC Commission Meeting

Schedule can be found on the Internet

at:

http://www.nrc.gov//SECY/smj/

schedule.htm

* * * * *

This notice is distributed by mail to

several hundred subscribers; if you no

longer wish to receive it, or would like

to be added to it, please contact the

Office of the Secretary, Attn: Operations

Branch, Washington, D.C. 20555 (301–

415–1661).

In addition, distribution of this

meeting notice over the internet system

is available. If you are interested in

receiving this Commission meeting

schedule electronically, please send an

electronic message to wmh@nrc.gov or

dkw@nrc.gov.

* * * * *

Dated: September 10, 1997.

William M. Hill, Jr.,

Secretary, Tracking Officer, Office of the

Secretary.

[FR Doc. 97–24555 Filed 9–11–97; 1:49 pm]

BILLING CODE 7590–01–M

NUCLEAR REGULATORY

COMMISSION

Draft Regulatory Guide; Issuance,

Availability

The Nuclear Regulatory Commission

has issued for public comment a draft of

a guide planned for its Regulatory Guide

Series. This series has been developed

to describe and make available to the

public such information as methods

acceptable to the NRC staff for

implementing specific parts of the

Commission’s regulations, techniques

used by the staff in evaluating specific

problems or postulated accidents, and

data needed by the staff in its review of

applications for permits and licenses.

The draft guide, temporarily

identified by its task number, DG–1060

(which should be mentioned in all

correspondence concerning this draft

guide), is titled ‘‘Financial Accounting

Standards Board (FASB) Standards for

Decommissioning Cost Accounting.’’

The guide is intended for Division 1,

‘‘Power Reactors.’’ This draft guide is

being developed to propose NRC’s

endorsement of the Financial

Accounting Standards Board draft

standard No. 158–B, ‘‘Accounting for

Certain Liabilities Related to Closure or

Removal of Long-Lived Assets.’’ (Copies

may be obtained from FASB, 401 Merritt

7, P.O. Box 5116, Norwalk, CT 06856–

5116.)

This Draft Regulatory Guide DG–1060

is being issued in anticipation of

rulemaking regarding the funding for

decommissioning power reactors. An

advance notice of proposed rulemaking

(ANPR) was published on April 8, 1996

(61 FR 15427). After consideration of

the responses, the staff believes it is

likely that the proposed rule will

include a periodic reporting

requirement. Issuance of a final

regulatory guide is dependent upon

issuance of a final rule that includes a

provision for a reporting requirement. In

the interest of efficiency and utility, the

staff is proposing to endorse this draft

FASB standard to facilitate licensees’

plans for decommissioning.

The draft guide has not received

complete staff review and does not

represent an official NRC staff position.

Public comments are being solicited

on Draft Regulatory Guide DG–1060.

Comments may be accompanied by

additional relevant information or

supporting data. Written comments may

be submitted to the Rules and Directives

Branch, Office of Administration, U.S.

Nuclear Regulatory Commission,

Washington, DC 20555. Copies of

comments received may be examined at

the NRC Public Document Room, 2120

L Street NW., Washington, DC.

Comments will be most helpful if

received by November 24, 1997.

Although a time limit is given for

comments on this draft guide,

comments and suggestions in

connection with items for inclusion in

guides currently being developed or

improvements in all published guides

are encouraged at any time.

You may also provide comments via

the NRC’s interactive rulemaking

website through the NRC home page

(http://www.nrc.gov). This site provides

the availability to upload comments as

files (any format), if your web browser

supports that function. For information

about the interactive rulemaking