Federal Register / Vol. 61, No. 99 / Tuesday, May 21, 1996 / Notices 25509

A copy of the submittal may be

viewed free of charge at the NRC Public

Document Room, 2120 L Street, NW

(Lower Level), Washington, DC.

Members of the public who are in the

Washington, DC, area can access the

submittal via modem on the Public

Document Room Bulletin Board (NRC’s

Advance Copy Document Library) NRC

subsystem at FedWorld, 703–321–3339.

Members of the public who are located

outside of the Washington, DC, area can

dial FedWorld, 1–800–303–9672, or use

the FedWorld Internet address:

fedworld.gov (Telnet). The document

will be available on the bulletin board

for 30 days after the signature date of

this notice. If assistance is needed in

accessing the document, please contact

the FedWorld help desk at 703–487–

4608. Additional assistance in locating

the document is available from the NRC

Public Document Room, nationally at 1–

800–397–4209, or within the

Washington, DC, area at 202–634–3273.

Comments and questions should be

directed to the OMB reviewer by June

20, 1996: Peter Francis, Office of

Information and Regulatory Affairs

(3150–0123), NEOB–10202, Office of

Management and Budget, Washington,

DC 20503.

Comments can also be submitted by

telephone at (202) 395–3084.

The NRC Clearance Officer is Brenda

Jo. Shelton, (301) 415–7233.

Dated at Rockville, Maryland, this 14th day

of May 1996.

For the Nuclear Regulatory Commission.

Gerald F. Cranford,

Designated Senior Official for Information

Resources Management.

[FR Doc. 96–12695 Filed 5–20–96; 8:45 am]

BILLING CODE 7590–01–P

[Docket Nos. 50–325 and 50–324]

Carolina Power & Light Company;

Notice of Withdrawal of Application for

Amendment to Facility Operating

License

The U.S. Nuclear Regulatory

Commission (the Commission) has

granted the request of Carolina Power &

Light Company (the licensee) to

withdraw its March 31, 1995,

application for proposed amendment to

Facility Operating License Nos. 50–325

and 50–324 for the Brunswick Steam

Electric Plant, Units 1 and 2, located in

Brunswick County, North Carolina.

The proposed amendment would

have provided an exception to

Technical Specification (TS) 3.0.4 that

would have permitted an operational

mode change of a unit if the second unit

was in cold shutdown or refueling

(Operational Conditions 4 or 5

respectively) and one of the second

unit’s offsite power circuits was

inoperable.

The Commission had previously

issued a Notice of Consideration of

Issuance of Amendment published in

the Federal Register on April 13, 1995

(60 FR 18860). However, by letter dated

December 20, 1995, the licensee

withdrew the proposed change.

For further details with respect to this

action, see the application for

amendment dated March 31, 1995, and

the licensee’s letter dated December 20,

1995, which withdrew the application

for license amendment. The above

documents are available for public

inspection at the Commission’s Public

Document Room, 2120 L Street NW.,

Washington, DC 20555, and at the

University of North Carolina at

Wilmington, William Madison Randall

Library, 601 S. College Road,

Wilmington, North Carolina 28403–

3297.

Dated at Rockville, Maryland, this 14th day

of May 1996.

For the Nuclear Regulatory Commission.

Brenda L. Mozafari,

Project Manager, Project Directorate II–1,

Division of Reactor Projects—I/II, Office of

Nuclear Reactor Regulation.

[FR Doc. 96–12697 Filed 5–20–96; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

Sunshine Act Meeting

AGENCY HOLDING THE MEETING: Nuclear

Regulatory Commission.

DATE: Weeks of May 20, 27, June 3, and

10, 1996.

PLACE: Commissioners’ Conference

Room, 11555 Rockville Pike, Rockville,

Maryland.

STATUS: Public and Closed.

MATTERS TO BE CONSIDERED:

Week of May 20

Wednesday, May 22

10:00 a.m.—Affirmation Session (PUBLIC

MEETING) (if needed).

2:00 p.m.—Briefing by International

Programs (CLOSED—Ex. 1).

Friday, May 24

9:30 a.m.—Meeting with Advisory

Committee on Reactor Safeguards

(ACRS) (PUBLIC MEETING). (Contact:

John Larkins, 301–415–7360)

Week of May 27—Tentative

Thursday, May 30

2:00 p.m.—Briefing on Status of Dry Cask

Storage Issues (PUBLIC MEETING).

(Contact: William Travers, 301–415–

8500)

Friday, May 31

10:00 a.m.—Briefing on NRC Inspection

Activities (PUBLIC MEETING). (Contact:

Bill Borchardt, 301–415–1257)

11:30 a.m.—Affirmation Session (PUBLIC

MEETING) (if needed).

Week of June 3—Tentative

Monday, June 3

10:00 a.m.—Briefing on Part 100 Final Rule

on Reactor Site Criteria (PUBLIC

MEETING). (Contact: Charles Ader, 301–

415–5622)

Thursday, June 6

3:30 p.m.—Affirmation Session (PUBLIC

MEETING) (if needed).

Week of June 10—Tentative

Tuesday, June 11

2:00 p.m.—Briefing on Status of Risk

Harmonizaiton (PUBLIC MEETING).

(Contact: Judith Greenwald, 301–415-

6635)

3:30 p.m.—Affirmaiton Session (PUBLIC

MEETING) (if needed).

The schedule for Commisison meetings is

subject to change on short notice. To verify

the status of meetings call (recording)—(301)

415–1292. Contact person for more

information: BIll Hill (301) 415–1661.

* * * * *

This notice is distributed by mail to several

hundred subscribers; if you no longer wish

to receive it, or would like to be added to it,

please contact the Office of the Secretary,

Attn: Operations Branch, Washington, D.C.

20555 (301–415–1963).

In addition, distribution of this meeting

notice over the internet system is available.

If you are interested in receiving this

Commission meeting schedule electronically,

please send an electronic message to

alb@nrc.gov or gkt@nrc.gov.

* * * * *

Dated: May 16, 1996.

Andrew L. Bates,

Senior Level Advisor, Office of the Secretary.

[FR Doc. 96–12811 Filed 5–17–96; 10:23 am]

BILLING CODE 7590–01–M

NUCLEAR REGULATORY

COMMISSION

[Docket No. 50–309]

Maine Yankee Atomic Power Company,

Maine Yankee Atomic Power Station;

Receipt of Petition for Director’s

Decision Under 10 CFR 2.206

Notice is hereby given that by letter

dated January 20, 1996, Friends of the

Coast—Opposing Nuclear Pollution

(Petitioner) requested that the Nuclear

Regulatory Commission (NRC) take

action with regard to the Maine Yankee

Nuclear Power Station (Maine Yankee),

licensed to Maine Yankee Atomic Power

Company (licensee).

Petitioner requests that the

Commission take expedited action to:
25510 Federal Register / Vol. 61, No. 99 / Tuesday, May 21, 1996 / Notices

(1) Suspend the operating license of

Maine Yankee pending resolution of the

Petition; (2) examine and test by plug

sampling—or other ASME approved

method—all large piping welds that

may have been susceptible to microfissures at the time of construction; (3)

reanalyze Maine Yankee containment as

one located in an area where seismic

risk is not ‘‘low’’; (4) reduce the licensed

operating capacity of Maine Yankee to

a level consistent with a flawed

containment and/or flawed reactor

coolant piping welds; (5) provide an

informal public hearing in the area of

the plant regarding the Petition; and (6)

place Petitioner on service and mailing

lists relevant to its interests in safety at

Maine Yankee and all public forums

opened by the NRC.

As the basis for these requests, the

Petition states that: (1) The containment

is inadequate for power operation in

excess of the original license, and may

be inadequate for the original power

operation limits because of

insupportable original design

acceptance criteria, yet the NRC staff

recommended to the Commission that it

grant a license amendment permitting

this design. It is further stated that the

Maine Yankee containment was

designed and constructed without

diagonal reinforcement rods, based on

low seismic risk. Additionally, after a

1979 earthquake of 4.2 magnitude and

an epicenter less than 10 miles from the

plant site, the NRC ordered the

shutdown of Maine Yankee until piping

and piping supports could be

seismically qualified. There is no public

record, however, that the NRC

reevaluated this marginally acceptable

containment design, including prior to

granting license amendments to operate

at increased power; and (2) the Maine

Yankee emergency core cooling system

(ECCS), reactor coolant piping, and

other large piping have not been

adequately analyzed for materials

degradation to ensure integrity at power

operation in excess of the originally

licensed power level, or under accident

conditions. The Atomic Energy

Commission’s concern with ‘‘microfissures’’ in reactor coolant system

welds led to appointment of a task force,

and prompted studies and reports in

1971 (prior to heightened awareness of

embrittlement phenomena) that

concluded that the microfissures would

not propagate or grow under foreseeable

conditions. The Petitioner asserts that

large pipe welds next to the reactor

vessel have endured 23 years of

corrosion, stress, vibration, and

radiation and may fail, initiating a lossof-coolant accident, or may be subject to

thermal shock failure initiated by use of

the ECCS.

The Petition has been referred to the

Director of the Office of Nuclear Reactor

Regulation (NRR) pursuant to 10 CFR

2.206. As provided by Section 2.206,

appropriate action will be taken on the

Petition within a reasonable time. By

letter dated May 13, 1996, the Director

denied the Petitioner’s request for

suspension of Maine Yankee’s operating

license, pending resolution of the

Petition.

A copy of the Petition is available for

inspection at the Commission’s Public

Document Room at 2120 L Street NW.,

Washington, D.C. 20555–0001 and the

local public document room in the

Wiscasset Public Library, High Street,

P.O. Box 367, Wiscasset, ME 04578.

Dated at Rockville, Maryland this 13th day

of May 1996.

For the Nuclear Regulatory Commission.

William T. Russell,

Director, Office of Nuclear Reactor

Regulation.

[FR Doc. 96–12693 Filed 5–20–96; 8:45 am]

BILLING CODE 7590–01–P

Regulatory Guide; Issuance,

Availability

The Nuclear Regulatory Commission

has issued a revision to a guide in 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.

Revision 2 of Regulatory Guide 1.82,

‘‘Water Sources for Long-Term

Recirculation Cooling Following a Lossof-Coolant Accident,’’ has been revised

to provide current guidance on methods

acceptable to the NRC staff for meeting

the Commission’s requirements with

respect to the sumps and suppression

pools that perform the functions of

water sources for emergency core

cooling, containment heat removal, and

containment atmosphere cleanup. This

guide also updates the guidance on

evaluating blockage by debris in the

sumps and suppression pools of boiling

water nuclear power reactors.

Comments and suggestions in

connection with items for inclusion in

guides currently being developed or

improvements in all published guides

are encouraged at any time. 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.

Regulatory guides are available for

inspection at the Commission’s Public

Document Room, 2120 L Street NW.,

Washington, DC. Single copies of

regulatory guides may be obtained free

of charge by writing the Office of

Administration, Attention: Distribution

and Services Section, U.S. Nuclear

Regulatory Commission, Washington,

DC 20555–0001, or by fax at (301) 415–

2260. Issued guides may also be

purchased from the National Technical

Information Service on a standing order

basis. Details on this service may be

obtained by writing NTIS, 5285 Port

Royal Road, Springfield, VA 22161.

Regulatory guides are not copyrighted,

and Commission approval is not

required to reproduce them.

(5 U.S.C. 552(a))

Dated at Rockville, Maryland, this 6th day

of May 1996.

For the Nuclear Regulatory Commission

Themis P. Speis,

Deputy Director, Office of Nuclear Regulatory

Research.

[FR Doc. 96–12696 Filed 5–20–96; 8:45 am]

BILLING CODE 7590–01–P

SECURITIES AND EXCHANGE

COMMISSION

[File No. 1–8627]

Issuer Delisting; Notice of Application

To Withdraw From Listing and

Registration; (Santa Fe Pacific Gold

Corporation, Common Stock, $0.01 Par

Value)

May 15, 1996.

Santa Fe Pacific Gold Corporation

(‘‘Company’’ or ‘‘SFPG’’) has filed an

application with the Securities and

Exchange Commission (‘‘Commission’’),

pursuant to Section 12(d) of the

Securities Exchange Act of 1934 (‘‘Act’’)

and Rule 12d2–2(d) promulgated

thereunder, to withdraw the above

specified security (‘‘Security’’) from

listing and registration on the Chicago

Stock Exchange, Inc. (‘‘CHX’’).

The reasons alleged in the application

for withdrawing the Security from

listing and registration include the

following:

According to the Company, the

Security of SFPG is currently traded on

the NYSE and the CHX. The Company

incurs annual fees for each of the

exchanges. Currently SFPG is paying an

annual fee of $2,500 to the CHX.

From time to time SFPG has issued

additional shares of Security for use in

connection with its employee benefit