13726 Federal Register / Vol. 62, No. 55 / Friday, March 21, 1997 / Notices

Dated at Rockville, Maryland, this 13th day

of March 1997.

For the Nuclear Regulatory Commission.

Joseph J. Holonich,

Chief, Uranium Recovery Branch, Division

of Waste Management, Office of Nuclear

Material Safety and Safeguards.

[FR Doc. 97–7182 Filed 3–20–97; 8:45 am]

BILLING CODE 7590–01–P

[50–282 AND 50–306]

Northern States Power Company;

Prairie Island Nuclear Generating

Plant, Units 1 and 2 Environmental

Assessment and Finding of No

Significant Impact

The U.S. Nuclear Regulatory

Commission (the Commission) is

considering issuance of an amendment

to the Facility Operating License Nos.

DPR–42 and DPR–60, issued to

Northern States Power Company, (the

licensee), for operation of the Prairie

Island Nuclear Generating Plants, Unit 1

and 2, respectively, located in Goodhue

County, Minnesota.

Environmental Assessment

Identification of the Proposed Action

The proposed action would allow

license amendments for Prairie Island

Nuclear Generating Plant, Units 1 and 2,

that resolve unreviewed safety questions

associated with post-seismic cooling

water source operations.

The proposed action is in accordance

with the licensee’s application for

amendments dated January 29, 1997, as

supplemented February 11, 12, March 7,

10, and 11, 1997.

The Need for the Proposed Action

The proposed action would revise the

cooling water system emergency intake

design bases. The proposed

amendments contain license conditions

that provide interim measures to resolve

unreviewed safety questions relating to

the cooling water system emergency

intake line. The interim measures

include the use of a dedicated operator

to identify a seismic event so that

nonessential cooling water loads can be

stripped and the cooling water load

demand can be reduced to within the

capacity of the seismically qualified

emergency intake pipe following a

design-basis earthquake. The use of the

dedicated operator will be eliminated

when the licensee is able to provide a

seismically qualified cooling water

source either through analyses or

modifications.

Environmental Impacts of the Proposed

Action

The Commission has completed its

evaluation of the proposed action and

concludes that pursuant to 10 CFR

50.90, the proposed amendments would

not significantly increase the probability

or consequences of accidents previously

analyzed and the proposed amendments

would not affect facility radiation levels

or facility radiological effluents.

The changes will not significantly

increase the probability or consequences

of accidents, no changes are being made

in the types of any effluents that may be

released offsite, and there is no increase

in the allowable individual or

cumulative occupational radiation

exposure. Accordingly, the Commission

concludes that there are no significant

radiological environmental impacts

associated with the proposed action.

With regard to potential

nonradiological impacts, the proposed

action does involve features located

entirely within the restricted area as

defined in 10 CFR Part 20. It does not

affect nonradiological plant effluents

and has no other environmental impact.

Accordingly, the Commission concludes

that there are no significant

nonradiological environmental impacts

associated with the proposed 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 Prairie Island Nuclear

Generating Plants, Units 1 and 2.

Agencies and Persons Consulted

In accordance with its stated policy,

on March 18, 1997, the staff consulted

with the Minnesota State official, Mr.

Michael McCarthy of the Department of

Public Services, 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 January 29, 1997, as

supplemented by letters dated February

11, 12, March 7, 10, and 11, 1997, which

are 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 located at the

Minneapolis Public Library, Technology

and Science Department, 300 Nicollet

Mall, Minneapolis, Minnesota 55401.

Dated at Rockville, Maryland, this 18th day

of March 1997.

For the Nuclear Regulatory Commission.

Beth Wetzel,

Project Manager, Project Directorate III–1,

Division of Reactor Projects—III/IV, Office of

Nuclear Reactor Regulation.

[FR Doc. 97–7318 Filed 3–20–97; 8:45 am]

BILLING CODE 7590–01–P

Nuclear Safety Research Review

Committee

AGENCY: Nuclear Regulatory

Commission.

ACTION: Notice of meeting.

The Nuclear Safety Research Review

Committee (NSRRC) will hold its next

meeting on April 3–4, 1997 in Room T–

10A1, Two White Flint North (TWFN)

Building, 11545 Rockville Pike,

Rockville, MD, from 9:00 a.m.—5:00

p.m. both days.

The meeting will be held in

accordance with the requirements of the

Federal Advisory Committee Act

(FACA) and will be open to public

attendance. The NSRRC provides advice

to the Director of the Office of Nuclear

Regulatory Research (RES) on matters of

overall management importance in the

direction of the NRC’s program of

nuclear safety research. The main

purpose of this meeting will be: (1) to

review the reports of the PRA/I&C and

Human Factors joint Subcommittee

meeting, the Accident Analysis

Subcommittee meeting, and the

Materials and Engineering

Subcommittee meeting; (2) discuss

research core competencies; and (3)

review Advisory Committee

effectiveness.

Participants in parts of the discussion

will include senior NRC staff and other

RES technical staff as necessary.

Members of the public may file

written statements regarding any matter
Federal Register / Vol. 62, No. 55 / Friday, March 21, 1997 / Notices 13727

to be discussed at the meeting. Members

of the public may also make requests to

speak at the meeting, but permission to

speak will be determined by the

Committee chairperson in accordance

with procedures established by the

Committee. A verbatim transcription

will be made of the NSRRC meeting and

a copy of the transcript will be placed

in the NRC’s Public Document Room in

Washington, DC.

Any inquiries regarding this notice or

any subsequent changes in the status

and schedule of the meeting, may be

made to the NSRRC Designated Federal

Officer, Dr. Jose Luis M. Cortez

(telephone: 301–415–6596), between

9:00 am and 5:00 pm. Persons planning

to attend these meetings are encouraged

to contact the above named individual

one or two business days before the

scheduled meeting to be advised of any

changes in schedule, etc., that may have

occurred.

Dated at Rockville, Maryland this 17th day

of March, 1997.

For the Nuclear Regulatory Commission.

Andrew L. Bates,

Federal Advisory Committee Management

Officer.

[FR Doc. 97–7176 Filed 3–20–97; 8:45 am]

BILLING CODE 7590–01–P

Regulatory Guides; Issuance and

Availability

The Nuclear Regulatory Commission

has issued for public comment drafts of

three guides for its Regulatory Guide

Series. This series has been developed

to describe and make available to the

public such information as methods

acceptable to the NRC staff for

implementing specific parts of the

Commission’s regulations, techniques

used by the staff in evaluating specific

problems or postulated accidents, and

data needed by the staff in its review of

applications for permits and licenses.

The draft guides are temporarily

identified by their task numbers, DG–

0006, DG–0007, and DG–0009 (which

should be mentioned in all

correspondence concerning these draft

guides). DG–0006, ‘‘Guide for the

Preparation of Applications for

Commercial Nuclear Pharmacy

Licenses,’’ is being developed to provide

guidance to applicants and licensees in

preparing applications for new licenses,

license amendments, and license

renewals for the possession, use, and

distribution of byproduct material in

commercial nuclear pharmacy

operations. DG–0007, ‘‘Guide for the

Preparation of Applications for Licenses

To Authorize Distribution of Various

Items to Commercial Nuclear

Pharmacies and Medical Use

Licensees,’’ is being developed to

provide guidance to applicants and

licensees on preparing applications for

new licenses, license amendments, and

license renewals for medical

distribution licenses under 10 CFR Part

32, ‘‘Specific Domestic Licenses To

Manufacture or Transfer Certain Items

Containing Byproduct Material.’’ DG–

0009, which is a proposed supplement

to Revision 2 to Regulatory Guide 10.8,

‘‘Guide for the Preparation of

Applications for Medical Use

Programs,’’ is being developed to

conform Regulatory Guide 10.8 with

current medical use regulations. DG–

0009 also proposes to add a new

appendix to Regulatory Guide 10.8,

Appendix Y, ‘‘Provisions for Research

Involving Human Subjects.’’ All three of

these guides are in conformance with

new medical use regulations (59 FR

61767) that became effective on January

1, 1996.

The development of these guides has

included coordination with the NRC’s

Advisory Committee on the Medical

Uses of Isotopes (which includes a

nuclear pharmacist), the NRC’s Medical

Visiting Fellow (a physician with

special expertise in nuclear medicine),

and a former NRC Medical Visiting

Fellow (a nuclear pharmacist).

These draft guides are being issued to

involve the public in the early stages of

the development of a regulatory position

in these areas. They have not received

complete staff review and do not

represent an official NRC staff position.

Public comments are being solicited

on the draft guides. Comments should

be accompanied by supporting data.

Written comments may be submitted to

the Rules Review and Directives Branch,

Division of Freedom of Information and

Publications Services, Office of

Administration, U.S. Nuclear Regulatory

Commission, Washington, DC 20555.

Comments will be most helpful if

received by July 31, 1997.

Comments may be submitted

electronically, in either ASCII text or

Wordperfect format (version 5.1 or

later), by calling the NRC Electronic

Bulletin Board on FedWorld. The

bulletin board may be accessed using a

personal computer, a modem, and one

of the commonly available

communications software packages, or

directly via Internet.

If using a personal computer and

modem, the NRC subsystem on

FedWorld can be accessed directly by

dialing the toll free number: 1–800–

303–9672. Communication software

parameters should be set as follows:

parity to none, data bits to 8, and stop

bits to 1 (N,8,1). Using ANSI or VT–100

terminal emulation, the NRC NUREGs

and RegGuides for Comment subsystem

can then be accessed by selecting the

‘‘Rules Menu’’ option from the ‘‘NRC

Main Menu.’’ For further information

about options available for NRC at

FedWorld, consult the ‘‘Help/

Information Center’’ from the ‘‘NRC

Main Menu.’’ Users will find the

‘‘FedWorld Online User’s Guides’’

particularly helpful. Many NRC

subsystems and databases also have a

‘‘Help/Information Center’’ option that

is tailored to the particular subsystem.

The NRC subsystem on FedWorld can

also be accessed by a direct dial phone

number for the main FedWorld BBS,

703–321–3339, or by using Telnet via

Internet, fedworld.gov. If using 703–

321–3339 to contact FedWorld, the NRC

subsystem will be accessed from the

main FedWorld menu by selecting the

‘‘Regulatory, Government

Administration and State Systems,’’

then selecting ‘‘Regulatory Information

Mall.’’ At that point, a menu will be

displayed that has an option ‘‘U.S.

Nuclear Regulatory Commission’’ that

will take you to the NRC Online main

menu. The NRC Online area also can be

accessed directly by typing ‘‘/go nrc’’ at

a FedWorld command line. If you access

NRC from FedWorld’s main menu, you

may return to FedWorld by selecting the

‘‘Return to FedWorld’’ option from the

NRC Online Main Menu. However, if

you access NRC at FedWorld by using

NRC’s toll-free number, you will have

full access to all NRC systems but you

will not have access to the main

FedWorld system.

If you contact FedWorld using Telnet,

you will see the NRC area and menus,

including the Rules menu. Although

you will be able to download

documents and leave messages, you will

not be able to write comments or upload

files (comments). If you contact

FedWorld using FTP, all files can be

accessed and downloaded but uploads

are not allowed; all you will see is a list

of files without descriptions (normal

Gopher look). An index file listing all

files within a subdirectory, with

descriptions, is included. There is a 15-

minute time limit for FTP access.

Although FedWorld can be accessed

through the World Wide Web, like FTP

that mode only provides access for

downloading files and does not display

the NRC Rules menu.

For more information on NRC bulletin

boards call Mr. Arthur Davis, Systems

Integration and Development Branch,

U.S. Nuclear Regulatory Commission,

Washington, DC 20555, telephone (301)

415–5780; e-mail AXD3@nrc.gov. For

more information on these draft

regulatory guides, contact Dr. D. Howe,