Federal Register / Vol. 65, No. 205 / Monday, October 23, 2000 / Notices 63265

Preservation and Access at the July 1,

2000 deadline.

Laura S. Nelson,

Advisory Committee Management Officer.

[FR Doc. 00–27139 Filed 10–20–00; 8:45 am]

BILLING CODE 7536–01–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

September 14, 2000, the National

Science Foundation published a notice

in the Federal Register of permit

applications received. A permit was

issued on October 13, 2000 to the

following applicant: Maria Stenzel,

Permit No. 2001–022.

Nadene G. Kennedy,

Permit Officer.

[FR Doc. 00–27161 Filed 10–20–00; 8:45 am]

BILLING CODE 7555–01–M

NUCLEAR REGULATORY

COMMISSION

[Docket No. 50–298]

Nebraska Public Power District; Notice

of Withdrawal of Application for

Amendment to Facility Operating

License

The U.S. Nuclear Regulatory

Commission (the Commission) has

granted the request of Nebraska Public

Power District (the licensee) to

withdraw its June 15, 1999, application

for proposed amendment to Facility

Operating License No. DPR–46 for the

Cooper Nuclear Station located in

Nemaha County, Nebraska.

The proposed amendment would

have revised the facility updated safety

analysis report on the containment

overpressure contribution to emergency

core cooling system pump net positive

suction head requirement post-loss-ofcoolant accident.

The Commission had previously

issued a Notice of Consideration of

Issuance of Amendment published in

the Federal Register on July 14, 1999

(64 FR 38031). However, by letter dated

June 14, 2000, the licensee withdrew the

proposed change.

For further details with respect to this

action, see the application for

amendment dated June 15, 1999, and

the licensee’s letter dated June 14, 2000

(Accession No. ML003724841), which

withdrew the application for license

amendment. The above documents are

available for public inspection at the

Commission’s Public Document Room,

the Gelman Building, 2120 L Street,

NW., Washington, DC, and accessible

electronically through the Adams Public

Electronic Reading Room link at the

NRC Web site (http://www.nrc.gov).

Dated at Rockville, Maryland, this 10th day

of October 2000.

For the Nuclear Regulatory Commission.

Mohan C. Thadani,

Senior Project Manager, Section 1, Project

Directorate IV & Decommissioning Division

of Licensing Project Management, Office of

Nuclear Reactor Regulation.

[FR Doc. 00–27177 Filed 10–20–00; 8:45 am]

BILLING CODE 7590–01–P

NUCLEAR REGULATORY

COMMISSION

[Docket Nos. 50–250 and 50–251]

Florida Power and Light Company,

Turkey Point Plant, Units 3 and 4;

Environmental Assessment and

Finding of No Significant Impact

The U.S. Nuclear Regulatory

Commission (NRC) is considering

issuance of an exemption from Title 10

of the Code of Federal Regulations (10

CFR) Part 50, Appendix G, for Facility

Operating License Nos. DPR–31 and

DPR–41, issued to Florida Power and

Light Company (FPL, the licensee), for

operation of the Turkey Point Plant,

Units 3 and 4, located in Dade County,

Florida.

Environmental Assessment

Identification of the Proposed Action

The proposed exemption would allow

FPL to apply the methodologies of the

American Society of Mechanical

Engineers (ASME) Code Cases N–588

and N–641 for the Turkey Point Plant

reactor vessel circumferential welds.

The proposed action is in accordance

with the licensee’s application for

exemption dated July 7, 2000, as

supplemented October 4, 2000.

The Need for the Proposed Action

10 CFR part 50, Appendix G, requires

that pressure-temperature (P/T) limits

be established for reactor pressure

vessels (RPVs) during normal operating

and hydrostatic pressure or leak-testing

conditions. Specifically, 10 CFR part 50,

Appendix G states that ‘‘The

appropriate requirements on both the

pressure-temperature limits and the

minimum permissible temperature must

be met for all conditions.’’ Appendix G

further specifies that the requirements

for these limits are the ASME Code,

Section XI, Appendix G Limits.

To address provisions of amendments

to the technical specification (TS) P/T

limits, low temperature overpressure

protection (LTOP) system setpoints and

LTOP system effective temperature

(Tenable), the licensee requested in its

submittals that the staff exempt Turkey

Point Units 3 and 4 from application of

specific requirements of 10 CFR part 50,

Section 50.60(a) and Appendix G, and

substitute use of ASME Code Cases N–

588 and N–641. Code Case N–588

permits the use of circumferentiallyoriented flaws in circumferential welds

for development of P/T limits. Code

Case N–641 permits the use of an

alternate reference fracture toughness

(KIC fracture toughness curve instead of

KIa fracture toughness curve) for reactor

vessel materials in determining the P/T

limits, LTOP setpoints and Tenable. Since

the KIC fracture toughness curve shown

in ASME Section XI, Appendix A,

Figure A–2200–1, provides greater

allowable fracture toughness than the

corresponding KIa fracture toughness

curve of ASME Section XI, Appendix G,

Figure G–2210–1 (the KIa fracture

toughness curve), using Code Case N–

641 for establishing the P/T limits,

LTOP setpoints and Tenable would be less

conservative than the methodology

currently endorsed by 10 CFR part 50,

Appendix G and, therefore, an

exemption to apply the Code Case

would be required by 10 CFR 50.60. It

should be noted that although the use of

the KIC fracture toughness curve in Code

Case N–641 was recently incorporated

into the Appendix G to Section XI of the

ASME Code, an exemption is still

needed because the proposed P/T limits,

LTOP setpoints and Tenable (excluding

Code Case N–641) are based on the 1996

edition (and 1997 addenda) of the

ASME Code.

Environmental Impacts of the Proposed

Action

The NRC has completed its evaluation

of the proposed action and concludes

that exemption from the requirements of

10 CFR part 50, Appendix G, to allow