13188 Federal Register / Vol. 60, No. 47 / Friday, March 10, 1995 / Notices

regulation is not necessary to achieve

the underlying purpose of the rule. The

licensee completed a successful ILRT

test during the fifth refueling outage for

Unit 2 and has developed a corrective

action plan for leakage through specific

containment penetrations. Strict

application of Appendix J would require

performance of another ILRT during the

sixth refueling outage in order to

address the additional testing

requirements of Appendix J, Section

III.A.6(b) and the Section III.D.1(a)

requirement to perform an ILRT during

the 10-year plant inservice inspections.

In order to avoid performance of an

ILRT during the sixth refueling outage,

the licensee has proposed a one-time

exemption from Section III.A.6(b)

(additional testing requirements) and a

permanent exemption from Section

III.D.1(a), in order to de-couple the

Appendix J ILRT test schedule and the

10-year inservice inspection periods.

Granting the exemption would result in

the performance of the next Unit 2 ILRT

during the seventh refueling outage,

which in consistent with the regular

testing interval of approximately once

per forty months.

The Need for the Proposed Action

The proposed exemption would allow

the licensee to resume a normal ILRT

testing interval and thereby preclude the

need to perform an ILRT during the

sixth refueling outage of LaSalle, Unit 2.

Performance of an ILRT during the

upcoming Unit 2 refueling outage would

result in the collection of significant

radiation dose, approximately 3 personrems, by licensee personnel. The need

for the exemption results from the

requirement to perform the ILRT during

refueling outages associated with the 10-

year plant inservice inspections and the

requirements to perform additional

ILRT testing in the event that

consecutive ILRT’s fail, even if those

failures are a result of leakage through

identified penetrations.

Environmental Impacts of the Proposed

Action

The Commission has completed its

evaluation of the proposed exemption

and concludes that granting the onetime relief from Section III.A.6(b) and

granting relief from Section III.D.1(a) of

Appendix J to 10 CFR part 50 does not

affect the configuration of plant systems

or plant operating practices. The

proposed exemption is limited to the

scheduling of a required Type A test

during the sixth refueling outage of Unit

2 and a subsequent decoupling of the

Type A tests from the inservice

inspection period. Previous testing has

demonstrated the integrity of the

containment structure. Leakage through

containment penetrations and values

would continue to be identified by

performance of LLRT. Therefore, no

increase in the release of radioactive

materials following an accident would

result from the revision of the Type A

test schedule. Changes to the Type A

test schedule do not affect the

radioactive effluent release during

normal operation. Accordingly, the

Commission concludes that this

proposed action would result in no

significant radiological environmental

impact.

With regard to potential

nonradiological impacts, the proposed

exemption only involves the scheduling

of ILRT testing. It does not affect

nonradiological plant effluents and

there are no other nonradiological

environmental impacts associated with

the proposed exemption.

Alternatives to the Proposed Action

Since the Commission concludes that

there are no significant environmental

impacts that would result from the

proposed action, any alternatives with

equal or greater environmental impacts

need not be evaluated. The principal

alternative would be to deny the

requested exemption and require the

licensee to conduct the ILRT during the

sixth refueling outage of LaSalle, Unit 2.

Denial would not significant reduce the

environmental impact of plant operation

and would result in lost electrical

generation and expense of significant

licensee resources.

Alternate Use of Resources

This action does not involve the use

of any resources not previously

considered in the Final Environmental

Statement for the LaSalle County

Station dated November 1978.

Agencies and Persons Contacted

The NRC staff reviewed the licensee’s

request and consulted with the Illinois

State official. The State Official had no

comments regarding the NRC’s

proposed action.

Finding of no Significant Impact

Based on the foregoing environmental

assessment, the Commission concludes

that the proposed action will not have

a significant effect on the quality of the

human environment. Accordingly, the

Commission has determined not to

prepare an environmental impact

statement for the proposed exemption.

For further details with respect to this

action, see the request for exemption

dated October 24, 1994, 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, the Public

Library of Illinois Valley Community

College, Rural Route No. 1, Oglesby,

Illinois.

Dated at Rockville, MD., this 1st day of

March 1995.

For the Nuclear Regulatory Commission.

George F. Dick, Jr.,

Acting Director, Project Directorate III–2,

Division of Reactor Projects III/IV, Office of

Nuclear Reactor Regulation.

[FR Doc. 95–5934 Filed 3–9–95; 8:45 am]

BILLING CODE 7590–01–M

Advisory Committee on Reactor

Safeguards Subcommittee Meeting on

Thermal Hydraulic Pheonomena;

Meeting

The ACRS Subcommittee on Thermal

Hydraulic Phenomena will hold a

meeting on March 27 and 28, 1995,

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 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, March 27,

1995–8:30 a.m. until the conclusion of

business and Tuesday, March 28, 1995–

8:30 a.m. until the conclusion of

business.

The Subcommittee will continue its

review of the NRC research program to

modify the RELAP5/MOD3 code for use

in the AP600 design certification

review. The focus of this meeting will

be on the development of the

Phenomena Identification and Tanking

Table (PRT) in this regard. 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 ask 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.
Federal Register / Vol. 60, No. 47 / Friday, March 10, 1995 / Notices 13189

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, its

consultants, 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 eningeer, Mr. Paul A.

Boehnert (telephone 301/415–8065)

between 7:30 a.m. and 4:15 p.m. (EST).

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 in the proposed

agenda, etc., that may have occurred.

Dated: March 6, 1995.

Sam Duraiswamy

Chief Nuclear Reactors Branch.

[FR Doc. 95–5935 Filed 3–9–95; 8:45 am]

BILLING CODE 7590–01–M

Advisory Committee on Reactor

Safeguards Meeting on Thermal

Hydraulic Phenomena; Meeting

The ACRS Subcommittee on Thermal

Hydraulic Phenomena will hold a

meeting on March 29 and 30, 1995,

Room T–2B1, 11545 Rockville Pike,

Rockville, Maryland.

The entire meeting will be closed to

public attendance to discuss

Westinghouse proprietary information

pursuant to (5 U.S.C. 552b(c)(4)), with

the exception of a one to two hour

portion that will be open to the public.

At this time, the open session is

scheduled to be held during the

afternoon of the second day (March 30,

1995) of the meeting.

The agenda for the subject meeting

shall be as follows:

Wednesday, March 29, 1995–8:30

a.m. until the conclusion of business

and Thursday, March 30, 1995–8:30

a.m. until the conclusion of business.

The Subcommittee will continue its

review of the Westinghouse test and

analysis programs associated with the

AP600 Passive Containment System.

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 statement 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

Westinghouse Electric Corporation,

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.

(EST). 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 in the proposed

agenda, etc., that may have occurred.

Dated: March 6, 1995.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 95–5936 Filed 3–9–95; 8:45 am]

BILLING CODE 7590–01–M

OFFICE OF PERSONNEL

MANAGEMENT

Notice of Request for Reclearance of

SF 2802, SF 2802B, and RI 36–7

AGENCY: Office of Personnel

Management.

ACTION: Notice.

SUMMARY: In accordance with the

Paperwork Reduction Act of 1980 (title

44, U.S. Code, chapter 35), this notice

announces a request for a reclearance of

an information collection. SF 2802,

Application for Refund of Retirement

Deductions (CSRS), must be completely

filled out and signed before OPM pays

a refund of retirement contributions. SF

2802B must also be complete if there are

spouse(s) or former spouse(s) who must

be notified of the employee’s intent to

take a refund. RI 36–7 is needed when

the SF 2802 is incomplete as to the

applicant’s marital status.

Approximately 35,000 SF 2802s are

completed annually. We estimate that it

takes 45 minutes to fill out the form. the

annual burden is 26,250 hours.

Approximately 31,500 SF 2802Bs are

completed annually. We estimate that it

takes 15 minutes to fill out the form. the

annual burden is 7,875 hours.

Approximately 21,050 RI 36–7s are

completed annually. We estimate that it

takes 10 minutes to fill out the form.

The annual burden is 3,508 hours. The

combined total annual burden is 37,633

hours.

For copies of this proposal, contact

Doris R. Benz on (703) 908–8564.

DATES: Comments on this proposal

should be received by no later than

April 10, 1995.

ADDRESSES: Send or deliver comments

to—

Lorraine E. Dettman, Retirement and

Insurance Group, Operations Support

Division, U.S. Office of Personnel

Management, 1900 E Street NW.,

Room 3349, Washington, DC 20415

and

Joseph Lackey, OPM Desk Officer,

Office of Information and Regulatory

Affairs, Office of Management and

Budget, New Executive Office

Building, NW, Room 10235,

Washington, DC 20503

FOR INFORMATION REGARDING

ADMINISTRATIVE COORDINATION CONTACT:

Mary Beth Smith-Toomey, Forms

Analysis and Design, (202) 606–0623.

Office of Personnel Management.

Lorraine A. Green,

Deputy Director.

[FR Doc. 95–5837 Filed 3–9–95; 8:45 am]

BILLING CODE 6325–01–M

Notice of Request for Reclearance of

Form SF 2800

AGENCY: Office of Personnel

Management.

ACTION: Notice.

SUMMARY: In accordance with the

Paperwork Reduction Act of 1980 (title

44, U.S. Code, chapter 35), this notice

announces a request for reclearance of

an information collection. Form SF

2800, Application for Death Benefits

Under the Civil Service Retirement