2422 Federal Register / Vol. 63, No. 10 / Thursday, January 15, 1998 / Notices

NATIONAL CREDIT UNION

ADMINISTRATION

Community Development Revolving

Loan Program for Credit Unions

AGENCY: National Credit Union

Administration.

ACTION: Notice of application period.

SUMMARY: The National Credit Union

Administration (NCUA) will accept

applications for participation in the

Community Development Revolving

Loan Program for Credit Unions

throughout calendar year 1998, subject

to availability of funds. Application

procedures for qualified low-income

credit unions are set forth in part 705,

NCUA Rules and Regulations, 12 CFR

Part 705.

DATES: Applications may be submitted

throughout calendar year 1998.

ADDRESSES: Applications for

participation may be obtained from and

should be submitted to: NCUA, Office of

Community Development Credit

Unions, 1775 Duke Street, Alexandria,

VA 22314–3428.

FOR FURTHER INFORMATION CONTACT: The

Office of Community Development

Credit Unions at the above address or

telephone (703) 518–6610.

SUPPLEMENTARY INFORMATION: Part 705 of

the NCUA Rules and Regulations

implements the Community

Development Revolving Loan Program

for Credit Unions. The purpose of the

Program is to assist officially designated

‘‘low-income’’ credit unions in

providing basic financial services to

residents in their communities which

result in increased income, ownership

and employment. The Program makes

available low interest loans and deposits

in amounts up to $300,000 to qualified

participating ‘‘low-income’’ credit

unions. Program participation is limited

to existing credit unions with an official

‘‘low-income’’ designation.

This notice is published pursuant to

section 705.9 of the NCUA Rules and

Regulations, 12 CFR 705.9, which states

that NCUA will provide notice in the

Federal Register when funds in the

program are available.

By the National Credit Union

Administration Board on January 8, 1998.

Becky Baker,

Secretary, NCUA Board.

[FR Doc. 98–968 Filed 1–14–98; 8:45 am]

BILLING CODE 7535–01–U

NATIONAL SCIENCE FOUNDATION

Notice of Permits Issued Under the

Antarctic Conservation Act of 1978

AGENCY: National Science Foundation.

ACTION: Notice of permits issued under

the Antarctic Conservation Act of 1978,

Public Law 95–541.

SUMMARY: The National Science

Foundation (NSF) is required to publish

notice of permits issued under the

Antarctic Conservation Act of 1978.

This is the required notice.

FOR FURTHER INFORMATION CONTACT:

Nadene G. Kennedy or Joyce Jatko

Permit Office, Office of Polar Programs,

Rm. 755, National Science Foundation,

4201 Wilson Boulevard, Arlington, VA

22230.

SUPPLEMENTARY INFORMATION: On

November 29, 1997, the National

Science Foundation published a notice

in the Federal Register of a waste

management permit application

received. A permit was issued on

December 24, 1997 to the following

applicant: Red Whittaker, Permit

#98WM–1.

Nadene G. Kennedy,

Permit Officer.

[FR Doc. 98–1055 Filed 1–14–98; 8:45 am]

BILLING CODE 7555–01–M

NATIONAL SCIENCE FOUNDATION

Notice of Permits Issued Under the

Antarctic Conservation Act of 1978

AGENCY: National Science Foundation.

ACTION: Notice of permits issued under

the Antarctic Conservation of 1978,

Public Law 95–541.

SUMMARY: The National Science

Foundation (NSF) is required to publish

notice of permits issued under the

Antarctic Conservation Act of 1978.

This is the required notice.

FOR FURTHER INFORMATION CONTACT:

Nadene G. Kennedy, Permit Office,

Office of Polar Programs, Rm. 755,

National Science Foundation, 4201

Wilson Boulevard, Arlington, VA 22230.

SUPPLEMENTARY INFORMATION: On

December 2, 1997, the National Science

Foundation published a notice in the

Federal Register of permit applications

received. Permits were issued on

January 7, 1998 to the following

applicants: Howard E. Evans, Permit No.

98–020 and Rennie S. Holt, Permit No.

98–021.

Nadene G. Kennedy,

Permit Officer.

[FR Doc. 98–1056 Filed 1–14–98; 8:45 am]

BILLING CODE 7555–01–M

NUCLEAR REGULATORY

COMMISSION

Agency Information Collection

Activities: Proposed Collection;

Comment Request

AGENCY: U.S. Nuclear Regulatory

Commission (NRC).

ACTION: Notice of pending NRC action to

submit an information collection

request to OMB and solicitation of

public comment.

SUMMARY: The NRC is preparing a

submittal to OMB for review of

continued approval of information

collections under the provisions of the

Paperwork Reduction Act of 1995 (44

U.S.C. Chapter 35).

Information pertaining to the

requirement to be submitted:

1. The title of the information

collection: NRC Form 366, ‘‘Licensee

Event Report’’.

2. Current OMB approval number:

3150–0104.

3. How often the collection is

required: On occasion.

4. Who is required or asked to report:

Holders of operating licenses for

commercial nuclear power plants.

5. The number of annual respondents:

109 holders of operating licenses for

commercial nuclear power plants.

6. The number of hours needed

annually to complete the requirement or

request: Approximately 50 hours per

response. The total industry burden is

80,000 hours.

7. Abstract: NRC collects reports of

operational events at commercial

nuclear power plants in order to

incorporate lessons of that experience in

the licensing process and to feed back

the lessons of that experience to the

nuclear industry.

Submit, by March 16, 1998, comments

that address the following questions:

1. Is the proposed collection of

information necessary for the NRC to

properly perform its functions? Does the

information have practical utility?

2. Is the burden estimate accurate?

3. Is there a way to enhance the

quality, utility, and clarity of the

information to be collected?

4. How can the burden of the

information collection be minimized,

including the use of automated

collection techniques or other forms of

information technology?

A copy of the draft supporting

statement may be viewed free of charge

at the NRC Public Document Room,

2120 L Street, NW (lower level),

Washington, DC. OMB clearance

requests are available at the NRC

worldwide web site (http://
Federal Register / Vol. 63, No. 10 / Thursday, January 15, 1998 / Notices 2423

www.nrc.gov) under the FedWorld

collection link on the home page tool

bar. The document will be available on

the NRC home page site for 60 days after

the signature date of this notice.

Comments and questions about the

information collection requirements

may be directed to the NRC Clearance

Officer, Brenda Jo. Shelton, U.S. Nuclear

Regulatory Commission, T–6 F33,

Washington, DC, 20555–0001, or by

telephone at 301–415–7233, or by

Internet electronic mail at

BJS1@NRC.GOV.

Dated at Rockville, Maryland, this 8th day

of January, 1998.

For the Nuclear Regulatory Commission.

Brenda Jo. Shelton,

NRC Clearance Officer, Office of the Chief

Information Officer.

[FR Doc. 98–1048 Filed 1–14–98; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket No. 50–302]

Florida Power Corporation; Notice of

Consideration of Issuance of

Amendment to Facility Operating

License, Proposed No Significant

Hazards Consideration Determination,

and Opportunity for a Hearing

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to Facility Operating License No. DPR

72, issued to the Florida Power

Corporation (FPC or the licensee), for

operation of the Crystal River Nuclear

Generating Unit 3 (CR3) located in

Citrus County, Florida.

The licensee proposed a revision to

the description of the starting logic for

the Reactor Building (RB) Recirculation

System Fan Coolers, as discussed in the

CR3 Final Safety Analysis Report

(FSAR), Chapters 5, 6, 7 and 9, and

Improved Technical Specification (ITS)

Bases Section 3.6. The change to the

starting logic would ensure that only

one RB Fan starts on an Engineered

Safeguards (ES) Reactor Building

Isolation and Cooling (RBIC) signal. A

modification to the plant will install

components that could increase the

probability of occurrence of a

malfunction of equipment important to

safety previously evaluated in the

FSAR. FPC has determined that

proposed changes to associated

electrical controls involve an

Unreviewed Safety Question (USQ).

Therefore, NRC review and approval are

required.

Before issuance of the proposed

license amendment, the Commission

will have made findings required by the

Atomic Energy Act of 1954, as amended

(the Act) and the Commission’s

regulations.

The Commission has made a

proposed determination that the

amendment request involves no

significant hazards consideration. Under

the Commission’s regulations in 10 CFR

50.92, this means that operation of the

facility in accordance with the proposed

amendment would not (1) involve a

significant increase in the probability or

consequences of an accident previously

evaluated; or (2) create the possibility of

a new or different kind of accident from

any accident previously evaluated; or

(3) involve a significant reduction in a

margin of safety. The licensee made its

request on December 5, 1997, and as

required by 10 CFR 50.91(a), and

provided its analysis of the issue of no

significant hazards consideration which

is presented below:

1. Does not involve a significant increase

in the probability or consequences of an

accident previously evaluated.

The change to the starting logic for the RB

Fans affects the ES equipment that responds

to mitigate an accident. The RB Fans are not

accident initiators and the change to the

starting logic cannot initiate an accident.

Therefore, the probability of occurrence of an

evaluated accident is not increased.

The RB Fan start logic change selects an

available RB Fan to run upon an RBIC

actuation, but only allows the operation of

one RB Fan to prevent overloading the SW

[Nuclear Services Closed Cycle Cooling]

System. The containment analysis for CR–3

assumes that one train of ES equipment is

available for accident mitigation, specifically,

one RB Fan and one RB Spray train for

containment cooling. The combination of two

RB Spray trains with no RB Fans is also

evaluated and found to be acceptable. These

available containment cooling equipment

combinations represent the minimum that

would be available for accident response

both before and after the implementation of

this change.

In addition to the same equipment being

available to mitigate an accident, there is no

change to the analyzed containment

response. The time delay in the start of an

RB Fan of up to several seconds due to the

modification has been evaluated through

containment analysis sensitivity studies. The

results of these studies show that

containment peak pressure and temperature,

and long term temperature profiles, are not

affected. The consequences of an accident are

directly related to containment pressure and

temperature conditions. Since containment

conditions following an accident are not

affected by this modification, there will be no

change to the consequences of any analyzed

accident.

2. Does not create the possibility of a new

or different kind of accident from any

accident previously evaluated.

The modification changes the RB Fan start

logic in the event of an accident. The new

start circuit ensures that one RB Fan is

operating in response to an RBIC actuation,

but prevents the operation of two fans. This

modification prevents the thermal

overloading of the SW System in order to

preserve the operability of equipment cooled

by the SW System. Several potential new

failure modes were evaluated and

determined not to create the possibility of a

new or different kind of accident.

Additionally, the RB Fans are engineered

safeguards equipment designed to mitigate an

accident, and the SW System is an accident

mitigation support system. These systems are

not accident initiators. The ES electrical

busses and the EDG [emergency diesel

generator] are not affected by this change. All

containment design conditions are met with

this change.

Therefore, this change cannot create the

possibility of an accident of a different kind

than previously evaluated in the SAR.

3. Does not involve a significant reduction

in the margin of safety.

Technical Specification 3.6.6 states that

two RB Spray trains and two RB containment

cooling trains must be operable. This

specification ensures diversity and

redundancy of the containment cooling

system. Following the modification, all

margins will be maintained. Two RB Fans

will be operable and capable of starting on

an RBIC signal. The modified circuitry

maintains the RB Fan redundancy. The RB

Sprays are not affected by this modification.

The margin of safety associated with the

containment maximum pressure and

temperature in response to a LOCA [loss-ofcoolant accident] is not affected since any

failure of this modification results in

equipment combinations that have been

analyzed and determined to be acceptable.

Containment LOCA response sensitivity

studies have verified that the small start

delay, associated with the modified RB Fan

start circuit, has no effect on the post-LOCA

peak temperature and pressure in

containment. Also, the failure of SW valves

that results in the loss of the ability of the

RB Fan Coolers to remove heat or the failure

of either RB Fan to run, will not affect the

containment peak temperature and pressure

conditions since two trains of RB Spray are

available.

The proposed modification allows only

one RB Fan to operate post-accident. This

ensures that the SW System is not overloaded

and SW temperatures remain within design

basis limits. Therefore, there is no reduction

in the margin of safety for the SW System

equipment cooling function after the

implementation of this change.

The small additional electrical loads, and

the out-of-sequence loading of an RB Fan

associated with this change have been

evaluated and determined to be within the

load limits of the EDG and ES electrical

busses. Therefore, there is no reduction in

the electrical system margin of safety.

Based on the above evaluation, there is no

reduction in the margin of safety associated

with the equipment and systems affected by

this change.