22620 Federal Register / Vol. 66, No. 87 / Friday, May 4, 2001 / Notices

T operating window, especially at low

temperature conditions. The operating

window becomes more restrictive with

continued reactor vessel service.

Implementation of the proposed P–T

curves, as allowed by ASME Code Case

N–640, does not significantly reduce the

margin of safety. Thus, pursuant to 10

CFR 50.12(a)(2)(ii), the underlying

purpose of the regulation will continue

to be served.

In summary, the ASME Section XI,

Appendix G procedure was

conservatively developed based on the

level of knowledge existing in 1974

concerning RPV materials and the

estimated effects of operation. Since

1974, the level of knowledge about these

topics has been greatly expanded. The

NRC staff concurs that this increased

knowledge permits relaxation of the

ASME Section XI, Appendix G

requirements by application of ASME

Code Case N–640, while maintaining,

pursuant to 10 CFR 50.12(a)(2)(ii), the

underlying purpose of the ASME Code

and the NRC regulations to ensure an

acceptable margin of safety.

3.0 Discussion

Pursuant to 10 CFR 50.12, the

Commission may, upon application by

any interested person or upon its own

initiative, grant exemptions from the

requirements of 10 CFR part 50, when

(1) the exemptions are authorized by

law, will not present an undue risk to

public health or safety, and are

consistent with the common defense

and security; and (2) when special

circumstances are present. The staff

accepts the licensee’s determination that

an exemption would be required to

approve the use of Code Case N–640.

The staff examined the licensee’s

rationale to support the exemption

request and concurred that the use of

the code case would also meet the

underlying intent of these regulations.

Based upon a consideration of the

conservatism that is explicitly

incorporated into the methodologies of

10 CFR part 50, Appendix G; Appendix

G of the ASME Code; and regulatory

guide (RG) 1.99, Revision 2, the staff

concluded that application of the code

case as described would provide an

adequate margin of safety against brittle

failure of the RPV. This is also

consistent with the determination that

the staff has reached for other licensees

under similar conditions based on the

same considerations. Therefore, the staff

concludes that requesting the exemption

under the special circumstances of 10

CFR 50.12(a)(2)(ii) is appropriate and

that the methodology of Code Case N–

640 may be used to revise the P–T limits

for the DAEC RCS.

4.0 Conclusion

Accordingly, the Commission has

determined that, pursuant to 10 CFR

50.12(a), the exemption is authorized by

law, will not endanger life or property

or common defense and security, and is,

otherwise, in the public interest.

Therefore, the Commission hereby

grants NMC an exemption from the

requirements of 10 CFR part 50,

§ 50.60(a) and 10 CFR part 50, Appendix

G, for the DAEC.

Pursuant to 10 CFR 51.32, an

environmental assessment and finding

of no significant impact has been

prepared and published in the Federal

Register (66 FR 20692). Accordingly,

based upon the environmental

assessment, the Commission has

determined that the granting of this

exemption will not result in any

significant effect on the quality of the

human environment.

This exemption is effective upon

issuance.

Dated at Rockville, Maryland, this 27th day

of April, 2001.

For the Nuclear Regulatory Commission.

Cynthia A. Carpenter,

Acting Director, Division of Licensing Project

Management, Office of Nuclear Reactor

Regulation.

[FR Doc. 01–11277 Filed 5–3–01; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket No. 40–8964]

Rio Algom Mining Corp.

AGENCY: Nuclear Regulatory

Commission.

ACTION: Final finding of no significant

impact; Notice of opportunity for

hearing.

SUMMARY: The U.S. Nuclear Regulatory

Commission (NRC) proposes to renew

NRC Source Material License SUA–1548

to authorize the licensee, Rio Algom

Mining Corporation (RAMC), to

continue commercial operations of its in

situ leach (ISL) Rio Algom Smith Ranch

Uranium Recovery Project in Converse

County, Wyoming. This license

currently authorizes RAMC to receive,

acquire, possess, and transfer uranium

at the Rio Algom Smith Ranch Project,

which is located approximately 17 miles

(27 Kilometers) Northeast of Glenrock,

Wyoming. An Environmental

Assessment (EA) was performed by the

NRC staff in support of its review of

RAMC renewal request, in accordance

with the requirements of 10 CFR part

51. The conclusion of the

Environmental Assessment is a Finding

of No Significant Impact (FONSI) for the

proposed licensing action.

FOR FURTHER INFORMATION CONTACT: Mr.

John H. Lusher, Fuel Cycle Licensing

Branch, Division of Fuel Cycle Safety

and Safeguards, Office of Nuclear

Material Safety and Safeguards, U.S.

Nuclear Regulatory Commission, Mail

Stop T8–A33, Washington, DC 20555.

Telephone 301/415–7694.

SUPPLEMENTARY INFORMATION:

Background

At the Rio Algom Smith Ranch

Facility, ISL uranium recovery method

involves: (1) The injection of native

groundwater, with added sodium

carbonate/bicarbonate and oxygen or

hydrogen peroxide, into uraniumbearing orebody through injection wells;

(2) the chemical mobilization of the

uranium through oxidation and then

complexation with the carbonate

species; and (3) the extraction of the

uranium-bearing solution from the

subsurface through a pattern of

pumping wells. The uranium is

separated from the leach solution by

conventional ion exchange methods in

the processing facility. The resulting

uranium-poor solution is recharged with

carbonate and oxygen and returned to

the leaching zone for additional

uranium recovery. This cycle continues

until the ore zone is depleted or

recovery of uranium is no longer

economically feasible.

The recovered uranium solution is

processed further by using ammonia or

hydrogen peroxide to precipitate the

uranium into a slurry. The resulting

slurry is thickened by gravity settling,

and then washed and de-watered in a

filter press to about 50 percent solids.

The filter press solids (cake) are then

dried in a natural gas heated oil vacuum

dryer, to produce uranium oxide, which

is commonly known as ‘‘yellowcake.’’

The dried yellowcake is packaged in 55-

gallon (208-liter) steel drums for storage

and eventual shipment to a fuel

processing facility.

RAMC conducts uranium recovery

operations within designated areas

(wellfield units) of the Rio Algom Smith

Ranch site. These wellfield units consist

of about 50 acres (20 hectars) in size. A

number of well patterns are installed in

each wellfield unit, with each pattern

typically including four injection wells

laid out in a roughly rectangular shape

and one centrally-located pumping

(production) well. Currently, RAMC is

conducting uranium recovery

operations in three wellfield units.

Federal Register / Vol. 66, No. 87 / Friday, May 4, 2001 / Notices 22621

Summary of the Environmental

Assessment

The NRC staff performed an appraisal

of the environmental impacts associated

with the continued operation of the Rio

Algom Smith Ranch ISL facility, in

accordance with 10 CFR part 51,

Licensing and Regulatory Policy

Procedures for Environmental

Protection. In conducting its appraisal,

the NRC staff considered the following

information: (1) RAMC’s license

renewal application, as amended; (2)

previous environmental evaluations of

the RAMC facility; (3) RAMC’s

amendment request submitted

subsequent to its renewal application,

and NRC staff approval of such request;

(4) data contained in required

environmental monitoring reports; (5)

results of NRC staff site visits and

inspections of the RAMC facility; and

(6) consultations with the U.S. Fish and

Wildlife Service, the U.S. Bureau of

Land Management, and the Wyoming

State Historic Preservation Officer. The

results of the staff’s appraisal are

documented in an Environmental

Assessment. The safety aspects for the

continued operation are discussed

separately in a Safety Evaluation Report

(SER).

The license renewal would authorize

RAMC to continue operating the Rio

Algom Smith Ranch ISL facility, such

that the plant and satellite facilities

throughput does not exceed a flow rate

of 12,000 gallons (45,420 liters) per

minute, exclusive of the flow involved

in restoring the depleted wellfield units.

Annual yellowcake production will not

be authorized to exceed 3.5 million

pounds (1,587,565 kilograms).

All conditions in the renewal license

and commitments presented in the

renewal application are subject to NRC

inspection. Violation of the license may

result in enforcement action.

Conclusions

The NRC staff has re-examined actual

and potential impacts associated with

continued commercial operation of the

Rio Algom Smith Ranch ISL facility,

and has determined that the renewal of

Source Material License SUA–1548 will:

(1) Be consistent with requirements of

10 CFR Part 40, (2) not be inimical to

the public health and safety; and (3) not

have long-term detrimental impacts on

the environment. The following

statements summarize the conclusions

resulting from the staff’s environmental

assessment, and support the FONSI:

1. The proposed ground water

monitoring program is sufficient to

detect excursions (vertical and

horizontal) of recovery solutions.

Furthermore, aquifer testing and

previous operations indicate that the

production zone is adequately confined,

thereby assuring hydrological control of

recovery solutions;

2. Liquid process waste will be

disposed in accordance with approved

waste disposal options. Monitoring

programs are in place to ensure

appropriate operation of the deep

disposal wells and to detect potential

leakage from the evaporation ponds;

3. An acceptable environmental and

effluent monitoring program is in place

to monitor effluent releases and to

detect if applicable regulatory limits are

exceeded. Radiological effluents from

facility operation have been and are

expected to remain below the regulatory

limits;

4. All radioactive waste generated by

facility operations will be disposed

offsite at a licensed 11e.(2) byproduct

disposal site;

5. Groundwater impacted by recovery

operations will be restored to baseline

conditions on a wellfield unit average,

as a primary goal. If baseline conditions

cannot be reasonably achieved, the R&D

operations have demonstrated that

groundwater can be restored to

applicable class-of-use standards; and

6. Because the staff has determined

that there will be no significant impacts

associated with approval of the license

renewal, there can be no

disproportionally high and adverse

effects or impacts on minority and lowincome populations. Consequently,

further evaluation of Environmental

Justice concerns, as outlined in

Executive Order 12898 and NRC’s Office

of Nuclear Material Safety and

Safeguards Policy and Procedures Letter

1–50, Revision 1, is not warranted.

Alternatives to the Proposed Action

The proposed action is to renew NRC

Source Material License SUA–1548, for

continued operation of the Rio Algom

Smith Ranch ISL facility as requested by

RAMC. Therefore, the principal

alternatives available to NRC are to:

(1) Renew the license with such

conditions as are considered necessary

or appropriate to protect public health

and safety and the environment; or

(2) Renew the license with such

conditions as are considered necessary

or appropriate to protect public health

and safety and the environment, but not

allow RAMC to expand its operations

beyond those previously approved; or

(3) Deny the renewal of the license.

Based on its review, the NRC staff has

concluded that the environmental

impacts associated with the proposed

action do not warrant either the limiting

of RAMC’s future operations or the

denial of the license renewal.

Additionally, in the SER prepared for

this action, the staff has reviewed the

licensee’s proposed action with respect

to the criteria for license issuance,

specified in 10 CFR part 40, § 40.32, and

has no basis for denial of the proposed

action. Therefore, the staff considers

that Alternative 1 is the appropriate

alternative for selection.

Finding of No Significant Impact

The NRC staff has prepared an EA for

the proposed renewal of NRC Source

Material License SUA–1548, On the

basis of this assessment, the NRC staff

has concluded that the environmental

impacts that may result from the

proposed action would not be

significant, and therefore, preparation of

an Environmental Impact Statement is

not warranted.

The EA and other documents related

to this proposed action are available for

public inspection and copying at the

NRC Public Document Room, One

White Flint North, 11555 Rockville

Pike, Rockville, MD 20852.

Notice of Opportunity for Hearing

The Commission hereby provides

notice that this is a proceeding on an

application for a licensing action falling

within the scope of 10 CFR part 2,

subpart L, ‘‘Informal Hearing Procedures

for Adjudications in Materials and

Operators Licensing Proceedings,’’ of

the Commission’s Rules of Practice for

Domestic Licensing Proceedings and

Issuance of Orders. Pursuant to

§ 2.1205(a), any person whose interest

may be affected by this proceeding may

file a request for a hearing. In

accordance with § 2.1205(d), a request

for a hearing must be filed within thirty

(30) days from the date of publication of

this Federal Register notice. The request

for a hearing must be filed with the

Office of the Secretary either:

(1) By delivery to the Rulemakings

and Adjudications Staff of the Office of

the Secretary at One White Flint North,

11555 Rockville Pike, Rockville, MD

20852; or (2) By mail or telegram

addressed to the Secretary, U.S. Nuclear

Regulatory Commission, Washington,

DC 20555, Attention: Rulemakings and

Adjudications Staff. In accordance with

10 CFR 2.1205(f), each request for a

hearing must also be served, by

delivering it personally or by mail to:

(1) The applicant, Rio Algom Mining

Corporation, 6305 Waterford Blvd, Suite

325, Oklahoma City, OK 73118;

(2) The NRC staff, by delivery to the

General Consel, One White Flint North,

11555 Rockville Pike, Rockville, MD

20852, or

22622 Federal Register / Vol. 66, No. 87 / Friday, May 4, 2001 / Notices

(3) By mail addressed to the Executive

Director for Operations, U.S. Nuclear

Regulatory Commission, Washington,

DC 20555.

In addition to meeting other

applicable requirements of 10 CFR part

2 of the Commission’s regulations, a

request for a hearing filed by a person

other than an applicant must describe in

detail:

(1) The interest of the requestor in the

proceeding;

(2) How that interest may be affected

by the results of the proceeding,

including the reasons why the requestor

should be permitted a hearing, with

particular reference to the factors set out

in § 2.1205(h);

(3) The requestor’s areas of concern

about the licensing activity that is the

subject matter of the proceeding; and

(4) The circumstances establishing

that the request for a hearing is timely

in accordance with § 2.1205(d).

Any hearing that is requested and

granted will be held in accordance with

the Commission’s ‘‘Informal Hearing

Procedures for Adjudications in

Materials and Operator Licensing

Proceedings’’ in 10 CFR part 2, subpart

L.

Dated at Rockville, Maryland, this 30th day

of April 2001.

For the Nuclear Regulatory Commission

Daniel M. Gillen,

Acting Chief, Fuel Cycle Licensing Branch,

Division of Fuel Cycle Safety and Safeguards,

Office of Nuclear Material Safety and

Safeguards.

[FR Doc. 01–11278 Filed 5–3–01; 8:45 am]

BILLING CODE 7590–01–P

POSTAL RATE COMMISSION

Commission Briefing

AGENCY: Postal Rate Commission.

ACTION: Notice of commission briefing.

SUMMARY: The Commission’s Office of

the Consumer Advocate will host a

briefing on two federal laws relating to

electronic signatures: the Uniform

Electronic Transactions Act and the

Electronic Signature in Global and

National Commerce Act. Mr. R. David

Whitaker will give the briefing.

DATES: Thursday, May 24, 2001, at 10:30

a.m.

ADDRESSES: The briefing will be held in

the Postal Rate Commission’s hearing

room, 1333 H St. NW., Suite 300,

Washington, DC 20268–0001.

FOR MORE INFORMATION CONTACT:

Stephen L.Sharfman, General Counsel,

202–789–6820.

Authority: 39 CFR 3002.7(a).

Dated: April 30, 2001.

Steven W. Williams,

Acting Secretary.

[FR Doc. 01–11200 Filed 5–3–01; 8:45 am]

BILLING CODE 7710–FW–M

POSTAL RATE COMMISSION

Tour of Printing and Distribution

Facilities

AGENCY: Postal Rate Commission.

ACTION: Notice of commission visit.

SUMMARY: In early May, Postal Rate

Commissioners and staff will tour

facilities of CTC Corp. and Quebecor

Inc. (both in Chicago, IL) and the United

Parcel Service (UPS) international air

hub (in Louisville, KY). The Quebecor

visit will include the logistics center,

consolidation facility, and bindery.

DATES: The visit is scheduled as follows:

May 7 (p.m.): CTC Corp.

May 8 (a.m.): Quebecor Inc.

May 8 (p.m.): United Parcel Service

FOR FURTHER INFORMATION CONTACT:

Stephen L. Sharfman, General Counsel,

Postal Rate Commission, Suite 300,

1333 H Street, NW., Washington, DC

20268–0001, 202–789–6820.

Dated: May 1, 2001.

Garry J. Sikora,

Acting Secretary.

[FR Doc. 01–11271 Filed 5–3–01; 8:45 am]

BILLING CODE 7710–FW–M

PRESIDIO TRUST

Notice of Public Meeting

AGENCY: The Presidio Trust.

ACTION: Notice of public meeting.

SUMMARY: In accordance with § 103(c)(6)

of the Presidio Trust Act, 16 U.S.C.

460bb note, Title I of Public Law 104–

333, 110 Stat. 4097, and in accordance

with the Presidio Trust’s bylaws, notice

is hereby given that a public meeting of

the Presidio Trust Board of Directors

will be held from 9:00 a.m. to 11:00 a.m.

on Wednesday, May 23, 2001, at the

Officers’ Club, 50 Moraga Avenue,

Presidio of San Francisco, California.

The Presidio Trust was created by

Congress in 1996 to manage

approximately eighty percent of the

former U.S. Army base known as the

Presidio, in San Francisco, California.

The purposes of this meeting are to:

(1) Receive staff reports regarding

environmental remediation, wildlife at

the Presidio, and historic building

rehabilitation; (2) receive a staff report

and take action regarding the Vegetation

Management Program; and (3) receive

public comment in accordance with the

Trust’s Public Outreach Policy.

Time: The meeting will be held from

9:00 a.m. to 11:00 a.m. on Wednesday,

May 23, 2001.

ADDRESSES: The meeting will be held at

the Officers’ Club, 50 Moraga Avenue,

Presidio of San Francisco.

FOR FURTHER INFORMATION CONTACT:

Craig Middleton, Deputy Director for

Operations and Governmental Affairs,

the Presidio Trust, 34 Graham Street,

P.O. Box 29052, San Francisco,

California 94129–0052, Telephone:

(415) 561–5300.

Dated: April 30, 2001.

Karen A. Cook,

General Counsel.

[FR Doc. 01–11222 Filed 5–3–01; 8:45 am]

BILLING CODE 4310–4R–U

RAILROAD RETIREMENT BOARD

Proposed Collection; Comment

Request

SUMMARY: In accordance with

requirement of section 3506 (c)(2)(A) of

the Paperwork Reduction Act of 1995

which provides opportunity for public

comment on new or revised data

collections, the Railroad Retirement

Board (RRB) will publish periodic

summaries of proposed data collections.

Comments are invited on: (a) Whether

the proposed information collection is

necessary for the proper performance of

the functions of the agency, including

whether the information has practical

utility; (b) the accuracy of the RRB’s

estimate of the burden of the collection

of the information; (c) ways to enhance

the quality, utility, and clarity of the

information to be collected; and (d)

ways to minimize the burden related to

the collection of information on

respondents, including the use of

automated collection techniques or

other forms of information technology.

Title and Purpose of Information

Collection: Verification of Supplemental

Annuity.

Under Section 2(b) of the Railroad

Retirement Act (RRA), the Railroad

Retirement Board (RRB) pays

supplemental annuities to qualified RRB

employee annuitants. A supplemental

annuity, which is computed according

to section 3(e) of the RRA, can be paid

at age 60 if the employee has at least 30

years of creditable railroad service or at

age 65 if the employee had 25–29 years

of railroad service. In addition to 25

years of service, a ‘‘current connection’’

with the railroad industry is required.

Eligibility is further limited to