Federal Register / Vol. 63, No. 107 /Thursday, June 4, 1998 / Notices 30521

NUCLEAR REGULATORY

COMMISSION

Advisory Committee on Nuclear

Waste; Renewal Notice

AGENCY: U.S. Nuclear Regulatory

Commission (NRC).

ACTION: Notice of renewal of the

Advisory Committee on Nuclear Waste

for a period of two years.

SUPPLEMENTARY INFORMATION: The

Nuclear Regulatory Commission has

determined that renewal of the Charter

for the Advisory Committee on Nuclear

Waste for the two year period

commencing on May 29, 1998, is in the

public interest in connection with

duties imposed on the Commission by

law. This action is being taken in

accordance with the Federal Advisory

Committee Act after consultation with

the Committee Management Secretariat,

General Services Administration.

The purpose of the Advisory

Committee on Nuclear Waste is to

provide advice to the U.S. Nuclear

Regulatory Commission (NRC) on

nuclear waste disposal facilities, as

directed by the Commission. This

includes 10 CFR parts 60 and 61 and

other applicable regulations and

legislative mandates. In performing its

work, the Committee will examine and

report on those areas of concern referred

to it by the Commission and may

undertake studies and activities on its

own initiative, as appropriate. Emphasis

will be on protecting the public health

and safety in the disposal of nuclear

waste. The Committee will interact with

representatives of NRC, ACRS, other

federal agencies, state and local

agencies, Indian Tribes, and private,

international and other organizations as

appropriate to fulfill its responsibilities.

FOR FURTHER INFORMATION PLEASE

CONTACT: John T. Larkins, Executive

Director of the Committee, U.S. Nuclear

Regulatory Commission, Washington,

DC 20555, telephone (301) 415–7360.

Dated: May 29, 1998.

Andrew L. Bates,

Federal Advisory Committee Management

Officer.

[FR Doc. 98–14771 Filed 6–3–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

Loss of Reactor Coolant Inventory and

Associated Potential for Loss of

Emergency Mitigation Functions While

in a Shutdown Condition; Issue

AGENCY: Nuclear Regulatory

Commission.

ACTION: Notice of issuance.

SUMMARY: The Nuclear Regulatory

Commission (NRC) has issued Generic

Letter (GL) 98–02 to all holders of

operating licenses for pressurized-water

reactors, except those who have

permanently ceased operations and

have certified that fuel has been

permanently removed from the reactor

vessel, to request that addressees (1)

assess the susceptibility of their residual

heat removal (RHR) and emergency core

cooling (ECC) systems to common-cause

failure as a result of reactor coolant

system (RCS) draindown while in a

shutdown condition, and (2) submit

certain information, pursuant to

§ 50.54(f) of Title 10 of the Code of

Federal Regulations (10 CFR 50.54(f)),

concerning their findings regarding

potential pathways for inadvertent RCS

drain-down and the suitability of

surveillance, maintenance, modification

and operating practices and procedures

regarding configuration control during

reactor shutdown cooling.

The generic letter is available in the

NRC Public Document Room under

accession number 9805050197.

DATES: The generic letter was issued on

May 28, 1998.

ADDRESSEES: Not applicable.

FOR FURTHER INFORMATION CONTACT:

Muhammad M. Razzaque, at (301) 415–

2882.

SUPPLEMENTARY INFORMATION: This

generic letter does not constitute a

backfit as defined in 10 CFR 50.109(a)(1)

since it does not impose modifications

of or additions to structures, systems or

components or to design or operation of

an addressee’s facility. It also does not

impose an interpretation of the

Commission’s rules that is either new or

different from a previous staff position.

The staff, therefore, has not performed

a backfit analysis.

Dated at Rockville, Maryland, this 28th day

of May 1998.

For the Nuclear Regulatory Commission.

Jack W. Roe,

Acting Director, Division of Reactor Program

Management, Office of Nuclear Reactor

Regulation.

[FR Doc. 98–14774 Filed 6–3–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

NRC Incident Response Function SelfAssessment; Public Meeting

AGENCY: Nuclear Regulatory

Commission.

ACTION: Notice of meeting.

SUMMARY: The NRC staff will solicit

public comment regarding the Incident

Response Function and suggestions for

initiatives that will improve the

efficiency and effectiveness of the

Incident Response Function.

DATES: June 16, 1998.

TIME: 1 pm–5 pm.

ADDRESSES: 11545 Rockville Pike,

Rockville Maryland 20852. Room T–

9A1.

FOR FURTHER INFORMATION CONTACT:

Stuart Rubin, Office for Analysis and

Evaluation of Operational Data, U.S.

Nuclear Regulatory Commission,

Washington DC 20555, Telephone (301)

415–7477.

SUPPLEMENTARY INFORMATION: In 1995,

the NRC conducted a review of NRC’s

major regulatory functions to identify

potential candidate programs for

improved efficiency. The review was

conducted in connection with the

National Performance Review for

Reinventing Government (NPR). In all,

seven programs were recommended in

NRC’s NPR task force report, SECY–95–

154, as warranting further detailed

review for efficiency improvement. One

of the programs identified was the

Incident Response Program. The

Commission responded that the

identified programs should be

considered as part of the NRC’s Strategic

Assessment and Rebaselining Initiative.

The specific efficiencies identified in

SECY–95–154 for the Incident Response

Program were considered by the staff

and either were implemented or are in

the process of being implemented, as

appropriate.

In assessing the NRC’s Incident

Response Function, the NRC’s Strategic

Assessment and Rebaselining Initiative,

the ‘‘related strategic issues’’ that will be

considered by the Self Assessment are:

(1) What measures should NRC take to

maintain a sufficient planning and

response capability for the Nuclear

Industry, State and local authorities,

and the Federal Government in the face

of growing economic pressure and

improving safety performance? (2) Is the

degree of NRC incident response

capability for materials and fuel facility

emergencies consistent with the risk

associated with the activities?

The overall goal and primary focus of

the Incident Response Function Self-