59008 Federal Register / Vol. 62, No. 211 / Friday, October 31, 1997 / Notices

required to prepare or cause to be

prepared environmental documents

relating to actions by the agency that

have significant impacts on the

environment. The Commission believes

that the NEPA process will be triggered

when a tribe and management

contractor seek approval of a

management contract under 25 CFR 533.

Respondents: Applicants seeking

approval of a management contract and/

or third party contractor.

Estimated Number of Respondents:

11.

Estimated Annual Responses: 11.

Estimated Annual Burden Hours:

5000.

Estimated Burden Hours Per

Response: 455.

Title: Annual Fees Payable by Class II

Gaming Operations.

OMB Number: 3141–0007.

Abstract: The IGRA authorizes the

NIGC to establish a schedule of fees to

be paid to the Commission by each class

II gaming operation regulated by the

IGRA. Fees are computed using rates set

by the NIGC and the assessable gross

revenues of each gaming operation. The

total of all fees assessed annually cannot

exceed $1,500,000. The required

information is needed for the NIGC to

both set and adjust rates and to support

the computation of fees paid by each

gaming operation.

Respondents: Class II gaming

operations.

Estimated Number of Respondents:

201.

Estimated Annual Responses: 404.

Estimated Burden Hours Per

Response: 5.

FOR COPIES AND FURTHER INFORMATION

CONTACT: Copies of documents

submitted to OMB may be obtained

from the National Indian Gaming

Commission, 1441 L Street NW, Suite

9100, Washington, DC 20005.

Tadd M. Johnson,

Chairman, National Indian Gaming

Commission.

[FR Doc. 97–28876 Filed 10–30–97; 8:45 am]

BILLING CODE 7567–01–M

NUCLEAR REGULATORY

COMMISSION

Application for a License To Import

Nuclear Waste

Pursuant to 10 CFR 110.70(b) ‘‘Public

notice of receipt of an application’’,

please take notice that the Nuclear

Regulatory Commission has received the

folowing application for an import

license. Copies of the application are on

file in the Nuclear Regulatory

Commission’s Public Document Room

located at 2120 L Street, N.W.,

Washington, D.C..

A request for a hearing or petition for

leave to intervene may be filed within

30 days after publication of this notice

in the Federal Register. Any request for

hearing or petition for leave to intervene

shall be served by the requestor or

petitioner upon the applicant, the Office

of the General Counsel, U.S. Nuclear

Regulatory Commission, Washington

D.C. 20555; the Secretary, U.S. Nuclear

Regulatory Commission, Washington,

D.C. 20555; and the Executive Secretary,

U.S. Department of State, Washington,

D.C. 20520.

The information concerning the

application follows.

NRC IMPORT LICENSE APPLICATION

Name of applicant, date of application, date received, application no.Description of material Country of

origin Material type Total qty End use

Chem-Nuclear Systems, October 14, 1997, October 20,

1997, IW005.

Contaminated Condenser

tubes and tube plates.

1.4 million ................................ Decontamination and recycling Taiwan.

For the Nuclear Regulatory Commission.

Dated this 24th day of October 1997 at

Rockville, Maryland.

Ronald D. Hauber,

Director, Division of Nonproliferation,

Exports and Multilateral Relations, Office of

International Programs.

[FR Doc. 97–28896 Filed 10–30–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket No. STN 50–457]

Commonwealth Edison Company;

Braidwood Station, Unit 2

Environmental Assessment and

Finding Of No Significant Impact

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an exemption

from certain requirements of its

regulations for Facility Operating

License No. NPF–77, issued to

Commonwealth Edison Company,

(ComEd, the licensee), for operation of

the Braidwood Station, Unit 2, located

in Will County, Illinois.

Environmental Assessment

Identification of the Proposed Action

The proposed action would permit

the licensee to use the alternate

methodology in American Society of

Mechanical Engineers (ASME) Boiler

and Pressure Vessel Code (Code) Case

N–514, ‘‘Low Temperature Overpressure

Protection,’’ to determine the low

temperature overpressure protection

(LTOP) system setpoints. By application

dated November 30, 1994, as

supplemented by letter dated May 11,

1995, the licensee requested an

exemption from certain requirements of

10 CFR 50.60, ‘‘Acceptance Criteria for

Fracture Prevention Measures for

Lightwater Nuclear Power Reactors for

Normal Operation.’’ The exemption

would allow application of an alternate

methodology to determine the LTOP

system setpoints for Braidwood, Unit 2.

The proposed alternate methodology is

consistent with guidelines developed by

the ASME Working Group on Operating

Plant Criteria to define pressure limits

during LTOP events that avoid certain

unnecessary operational restrictions,

provide adequate margins against failure

of the reactor pressure vessel, and

reduce the potential for unnecessary

activation of pressure relieving devices

used for LTOP. These guidelines have

been incorporated into the 1993

Addenda to the ASME Code, Section XI,

Appendix G. However, 10 CFR 50.55a,

‘‘Codes and Standards,’’ has not been

updated to reflect the acceptability of

the 1993 Addenda to the ASME Code.

The Need for the Proposed Action

Pursuant to 10 CFR 50.60, all

lightwater nuclear power reactors must

meet the fracture toughness

requirements for the reactor coolant

pressure boundary as set forth in 10 CFR
Federal Register / Vol. 62, No. 211 / Friday, October 31, 1997 / Notices 59009

Part 50, Appendix G. Appendix G of 10

CFR Part 50 defines pressuretemperature (P–T) limits during any

condition of normal operation,

including anticipated operational

occurrences and system hydrostatic

tests to which the pressure boundary

may be subjected over its service

lifetime, and specifies that these P–T

limits must be at least as conservative as

the limits obtained by following the

methods of analysis and the margins of

safety of the ASME Code, Section XI,

Appendix G. It is required in 10 CFR

50.55a that any reference to the ASME

Code, Section XI, in 10 CFR Part 50

refers to addenda through the 1988

Addenda and editions through the 1989

Edition of the Code unless otherwise

noted. It is specified in 10 CFR 50.60(b)

that alternatives to the described

requirements in 10 CFR Part 50,

Appendix G, may be used when an

exemption is granted by the

Commission under 10 CFR 50.12.

To prevent transients that would

produce excursions exceeding the P–T

limits while the reactor is operating at

low temperatures, the licensee installed

the LTOP system, which includes

pressure relieving devices called poweroperated relief valves (PORVs). The

PORVs prevent the pressure in the

reactor vessel from exceeding the P–T

limits. However, to prevent the PORV

from lifting as a result of normal

operating pressure surges, some margin

is needed between the normal operating

pressure and the PORV setpoint. In

addition, normal operating pressure

must be high enough to prevent damage

to reactor coolant pumps that may result

from cavitation or inadequate

differential pressure across the pump

seals. Hence, the licensee must operate

the plant in a pressure window that is

defined as the difference between the

minimum pressure required for reactor

coolant pumps and the operating margin

to prevent lifting of the PORVs. When

instrument uncertainty is considered,

the operating window is small and

presents difficulties for plant operation.

To meet the 10 CFR Part 50,

Appendix G, P–T limits, the PORVs

would be set to open at a pressure very

close to the normal pressure inside the

reactor. With the PORV setpoint close to

the normal operating pressure, minor

pressure perturbations that typically

occur in the reactor could cause the

PORVs to open. This is undesirable

from the safety perspective because after

every PORV opening there is some

concern that the PORV may not reclose.

A stuck open PORV would continue to

discharge primary coolant and reduce

reactor pressure until the discharge

pathway was closed by operator action.

The licensee requested use of the

ASME Code Case N–514, ‘‘Low

Temperature Overpressure Protection,’’

for the determination of the PORV

setpoints. This code case would permit

a slightly higher PORV setpoint during

low-temperature shutdown conditions.

This would reduce the likelihood for

inadvertent opening of the PORVs.

Appendix G of the ASME Code

requires that the P–T limits be

calculated: (a) using a safety factor of

two on the principal membrane

(pressure) stresses, (b) assuming a flaw

at the surface with a depth of one

quarter (1⁄4) of the vessel wall thickness

and a length of six (6) times its depth,

and (c) using a conservative fracture

toughness curve that is based on the

lower bound of static, dynamic, and

crack arrest fracture toughness tests on

material similar to the Braidwood

reactor vessel material.

ASME Code Case N–514 requires that

the system pressure is maintained below

the P–T limits during normal operation,

but allows the pressure that may occur

with the activation of pressure relieving

devices (PORVs) to exceed the P–T

limits, provided acceptable margins are

maintained during these events. This

approach protects the pressure vessel

from LTOP events, and maintains the

Technical Specification P-T limits

applicable for normal heatup and

cooldown in accordance with 10 CFR

Part 50, Appendix G, and Sections III

and XI of the ASME Code.

In determining the PORV setpoint for

LTOP events, the licensee proposed to

use the safety margins of ASME Code

Case N–514. This alternate methodology

allows determination of the setpoint for

LTOP events such that the maximum

pressure in the vessel will not exceed

110 percent of the P–T limits. This

results in a safety factor of 1.8 on the

principal membrane stresses. All other

factors, including the assumed flaw size

and fracture toughness, remain the

same. Although this methodology

would reduce the safety factor on the

principal membrane stresses, use of the

proposed criteria will provide adequate

margins of safety for the reactor vessel

during LTOP events.

Use of the Code Case N–514 safety

margins will reduce operational

challenges during low temperature, low

pressure operations. In terms of overall

safety, the safety benefits derived from

simplified operations and the reduced

potential for undesirable opening of the

PORVs will more than offset the

reduction of the principal membrane

safety factor. Reduced operational

challenges will reduce the potential for

undesirable impacts to the environment.

Environmental Impacts of the Proposed

Action

The proposed action involves features

located entirely within the protected

area as defined in 10 CFR Part 20.

The proposed action will not result in

an increase in the probability or

consequences of accidents or result in a

change in occupational or offsite dose.

Therefore, there are no radiological

impacts associated with the proposed

action.

The proposed action will not result in

a change in nonradiological plant

effluent and will have no other

nonradiological environmental impact.

Accordingly, the Commission

concludes that there are no

environmental impacts associated with

this action.

Alternatives to the Proposed Action

Since the Commission has concluded

there is no measurable environmental

impact associated with the proposed

action, any alternatives with equal or

greater environmental impact need not

be evaluated. As an alternative to the

proposed action, the staff considered

denial of the proposed action. Denial of

the application would result in no

change in current environmental

impacts. The environmental impacts of

the proposed action and the alternative

action are similar.

Alternative Use of Resources

This action does not involve the use

of any resources not previously

considered in the Final Environmental

Statement for the Braidwood Station.

Agencies and Persons Consulted

In accordance with its stated policy,

on October 22, 1997, the staff consulted

with the Illinois State official, Frank

Niziolek of the Illinois Department of

Nuclear Safety, regarding the

environmental impact of the proposed

action. The State official had no

comments.

Finding of No Significant Impact

Based upon the 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 action.

For further details with respect to the

proposed action, see the licensee’s letter

dated November 30, 1994, as

supplemented by letter dated May 11,

1995, which are available for public

inspection at the Commission’s Public

Document Room, The Gelman Building,

2120 L Street, NW., Washington, DC,
59010 Federal Register / Vol. 62, No. 211 / Friday, October 31, 1997 / Notices

and at the local public document room

located at the Wilmington Public

Library, 201 S. Kankakee Street,

Wilmington, Illinois 60481.

Dated at Rockville, Maryland, this 23rd day

of October 1997.

For the Nuclear Regulatory Commission.

George F. Dick, Jr.,

Senior Project Manager, Project Directorate

III–2, Division of Reactor Projects III/IV, Office

of Nuclear Reactor Regulation.

[FR Doc. 97–28881 Filed 10–30–97; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

Advisory Committee on Reactor

Safeguards Meeting of the ACRS

Subcommittee on Reliability and

Probabilistic Risk Assessment;

Revised

A meeting of the ACRS Subcommittee

on Reliability and Probabilistic Risk

Assessment scheduled to be held on

November 13-14, 1997 has been

rescheduled for Wednesday, November

12, 1997 and Thursday, November 13,

1997, Room T–2B3, 11545 Rockville

Pike, Rockville, Maryland. Notice of this

meeting was published in the Federal

Register on Friday, October 24, 1997 (62

FR 55435).

The entire meeting will be open to

public attendance.

The agenda for the subject meeting

shall be as follows:

Wednesday, November 12, 1997—8:30

a.m. until the conclusion of business

Thursday, November 13, 1997—8:30

a.m. until the conclusion of business

The Subcommittee will review the

proposed final Standard Review Plan

(SRP) Chapter 19 and associated

Regulatory Guide DG-1061(General

Guidance) for risk-informed,

performance-based regulation. The

Subcommittee will continue its review

of the matter included in the Staff

Requirements Memorandum dated May

27, 1997, regarding the use of

uncertainty versus point values in the

PRA-related regulatory decisionmaking

process. The Subcommittee will discuss

policy issues related to performancebased regulation, including industry

initiatives in this area. All other items

regarding this meeting remain the same

as announced in the Federal Register

published on Friday, October 24, 1997

(62 FR 55435).

Further information regarding this

meeting can be obtained by contacting

the cognizant ACRS staff engineer, Mr.

Michael T. Markley (telephone 301/

415–6885) between 7:30 a.m. and 4:15

p.m. (EST).

Dated: October 27, 1997.

Sam Duraiswamy,

Chief, Nuclear Reactors Branch.

[FR Doc. 97–28895 Filed 10–30–97; 8:45 am]

BILLING CODE 7590–01–P

SMALL BUSINESS ADMINISTRATION

[License No. 03/73–0212]

CEO Venture Fund III, L.P.; Notice of

Issuance of a Small Business

Investment Company License

On December 26, 1996, an application

was filed by CEO Venture Fund III, L.P.,

at 2000 Technology Drive, Suite 160,

Pittsburgh, Pennsylvania 15219–3109,

with the Small Business Administration

(SBA) pursuant to Section 107.300 of

the Regulations governing small

business investment companies (13

C.F.R. 107.300 (1996)) for a license to

operate as a small business investment

company.

Notice is hereby given that, pursuant

to Section 301(c) of the Small Business

Investment Act of 1958, as amended,

after having considered the application

and all other pertinent information, SBA

issued License No. 03/73–0212 on

August 1, 1997, to CEO Venture Fund

III, L.P. to operate as a small business

investment company.

(Catalog of Federal Domestic Assistance

Program No. 59.011, Small Business

Investment Companies)

Dated: October 22, 1997.

Don A. Christensen,

Associate Administrator for Investment.

[FR Doc. 97–28907 Filed 10–30–97; 8:45 am]

BILLING CODE 8025–01–P

SMALL BUSINESS ADMINISTRATION

Revocation of License of Small

Business Investment Company

Pursuant to the authority granted to

the United States Small Business

Administration by the Final Order of the

United States District Court for the

Eastern District of New York, dated

September 23, 1997, the United States

Small Business Administration hereby

revokes the license of S & S Venture

Associates, Ltd., a New York

corporation, to function as a small

business investment company under the

Small Business Investment Company

License No. 02/02–0383 issued to S & S

Venture Associates, Ltd. on April 25,

1980 and said license is hereby declared

null and void as of October 21, 1997.

United States Small Business

Administration.

Dated: October 21, 1997.

Don A. Christensen,

Associate Administrator for Investment.

[FR Doc. 97–28905 Filed 10–30–97; 8:45 am]

BILLING CODE 8025–01–P

SMALL BUSINESS ADMINISTRATION

Revocation of License of Small

Business Investment Company

Pursuant to the authority granted to

the United States Small Business

Administration by the Final Order of the

United States District Court for the

Eastern District of Pennsylvania, entered

August 15, 1997, the United States

Small Business Administration hereby

revokes the license of Salween Financial

Services, Inc., a Pennsylvania

corporation, to function as a small

business investment company under the

Small Business Investment Company

License No. 03/03–5157 issued to

Salween Financial Services, Inc. on July

1, 1983 and said license is hereby

declared null and void as of October 15,

1997.

United States Small Business

Administration.

Dated: October 15, 1997.

Don A. Christensen,

Associate Administrator for Investment.

[FR Doc. 97–28906 Filed 10–30–97; 8:45 am]

BILLING CODE 8025–01–P

SOCIAL SECURITY ADMINISTRATION

Information Collection Activities:

Proposed Collection Requests and

Comment Requests

This notice lists information

collection packages that will require

submission to the Office of Management

and Budget (OMB), as well as

information collection packages

submitted to OMB for clearance, in

compliance with PL. 104–13 effective

October 1, 1995, The Paperwork

Reduction Act of 1995.

I. The information collection(s) listed

below require(s) extension(s) of the

current OMB approval(s) or are

proposed new collection(s):

1. Request to be Selected as Payee—

0960–0014. The information collected

on Form SSA–11–BK is used to

determine the proper payee for a Social

Security beneficiary, and it is designed

to aid in the investigation of a payee

applicant. The form will establish the

applicant’s relationship to the

beneficiary, the justification, the

concern for the beneficiary and the

manner in which the benefits will be

used. The respondents are applicants for