50986 Federal Register / Vol. 72, No. 171 / Wednesday, September 5, 2007 / Notices 

ADDRESSES: National Aeronautics and 

Space Administration Headquarters, 300 

E Street, SW., Room 6H45, Washington, 

DC 20546. 

FOR FURTHER INFORMATION CONTACT: Dr. 

Glen R. Asner, Office of External 

Relations, (202) 358–0903, National 

Aeronautics and Space Administration, 

Washington, DC 20546–0001. 

SUPPLEMENTARY INFORMATION: This 

meeting will be open to the public up 

to the seating capacity of the room. Five 

seats will be reserved for members of 

the press. The agenda for the meeting is 

as follows: 

—To assess the operational readiness of 

the International Space Station to 

support a new crew. 

—To assess the Russian and American 

flight teams’ preparedness to 

accomplish the Expedition Sixteen 

mission. 

—To assess the health and flight 

readiness of the Expedition Sixteen 

crew. 

Attendees will be requested to sign a 

register and to comply with NASA 

security requirements, including the 

presentation of a valid picture ID, before 

receiving an access badge. Foreign 

nationals attending this meeting will be 

required to provide the following 

information: Full name; gender; date/ 

place of birth; citizenship; visa/green 

card information (number, type, 

expiration date); passport information 

(number, country, expiration date); 

employer/affiliation information (name 

of institution, address, country, phone); 

title/position of attendee. To expedite 

admittance, attendees should provide 

identifying information in advance by 

contacting Glen Asner via e-mail at 

glen.asner@nasa.gov or by telephone at 

(202) 358–0903 by September 21, 2007. 

It is imperative that the meeting be held 

on this date to accommodate the 

scheduling priorities of the key 

participants. 

Dated: August 24, 2007. 

P. Diane Rausch, 

Advisory Committee Management Officer, 

National Aeronautics and Space 

Administration. 

[FR Doc. E7–17468 Filed 9–4–07; 8:45 am] 

BILLING CODE 7510–13–P 

NATIONAL TRANSPORTATION 

SAFETY BOARD 

Agenda; Sunshine Act Meeting 

TIME AND DATE: 9:30 a.m., Tuesday, 

September 11, 2007. 

PLACE: NTSB Conference Center, 429 

L’Enfant Plaza SW., Washington, DC 

20594. 

STATUS: The two items are open to the 

public. 

MATTER TO BE CONSIDERED: 1124C, 

Motorcycle Safety Recommendation 

Letters. 

7833a, Railroad Accident Report—

Derailment of Chicago Transit Authority 

Train Number 220 Between Clark/Lake 

and Grand/Milwaukee Stations, 

Chicago, Illinois, July 11, 2006. 

NEWS MEDIA CONTACT: Telephone: (202) 

314–6100. 

Individuals requesting specific 

accommodations should contact Chris 

Bisett at (202) 314–6305 by Friday, 

September 7, 2007. 

The public may view the meeting via 

alive or archived webcast by accessing 

a link under ‘‘News & Events’’ on the 

NTSB home page at http:// 

www.ntsb.gov. 

FOR MORE INFORMATION CONTACT: Vicky 

D’Onofrio, (202) 314–6410. 

Dated: August 31, 2007. 

Vicky D’Onofrio, 

Federal Register Liaison Officer. 

[FR Doc. 07–4352 Filed 8–31–07; 12:52 pm] 

BILLING CODE 7533–01–M 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–237 and 50–249] 

Exelon Generation Company, LLC; 

Notice of Consideration of Issuance of 

Amendment to Renewed Facility 

Operating License No. DPR–19 and 

Renewed Facility Operating License 

No. DPR–25; Proposed No Significant 

Hazards Consideration Determination, 

and Opportunity for a Hearing 

The U.S. Nuclear Regulatory 

Commission (the Commission) is 

considering issuance of an amendment 

to Renewed Facility Operating License 

No. DPR–19 and Renewed Facility 

Operating License No. DPR–25 issued to 

Exelon Generation Company, LLC, (the 

licensee) for operation of the Dresden 

Nuclear Power Station, Units 2 and 3 

(DNPS), located in Grundy County, 

Illinois. 

The proposed amendment would 

revise the values of the safety limit 

minimum critical power ratio (SLMCPR) 

in Technical Specification Section 2.1.1, 

‘‘Reactor Core SLs.’’ The amendment 

request is being re-noticed because the 

Nuclear Regulatory Commission staff 

determined during the review of the 

licensee’s request that the change 

affected the licenses for both units at the 

DNPS. This notice supersedes the notice 

that appeared on July 31, 2007 (72 FR 

41783). 

Before issuance of the proposed 

license amendment, the Commission 

will have made findings required by the 

Atomic Energy Act of 1954, as amended 

(the Act), and the Commission’s 

regulations. 

The Commission has made a 

proposed determination that the 

amendment request involves no 

significant hazards consideration. Under 

the Commission’s regulations in Title 10 

of the Code of Federal Regulations (10 

CFR), Section 50.92, this means that 

operation of the facility in accordance 

with the proposed amendment would 

not (1) involve a significant increase in 

the probability or consequences of an 

accident previously evaluated; or (2) 

create the possibility of a new or 

different kind of accident from any 

accident previously evaluated; or (3) 

involve a significant reduction in a 

margin of safety. As required by 10 CFR 

50.91(a), the licensee has provided its 

analysis of the issue of no significant 

hazards consideration, which is 

presented below: 

1. Does the proposed change involve a 

significant increase in the probability or 

consequences of an accident previously 

evaluated? 

Response: No. 

The probability of an evaluated accident is 

derived from the probabilities of the 

individual precursors to that accident. The 

consequences of an evaluated accident are 

determined by the operability of plant 

systems designed to mitigate those 

consequences. Limits have been established 

consistent with NRC approved methods to 

ensure that fuel performance during normal, 

transient, and accident conditions is 

acceptable. The proposed change 

conservatively establishes the SLMCPR for 

DNPS Unit 2, Cycle 21 such that the fuel is 

protected during normal operation and 

during plant transients or anticipated 

operational occurrences (AOOs). 

Changing the SLMCPR does not increase 

the probability of an evaluated accident. The 

change does not require any physical plant 

modifications, physically affect any plant 

components, or entail changes in plant 

operation. Therefore, no individual 

precursors of an accident are affected. 

The proposed change revises the SLMCPR 

to protect the fuel during normal operation 

as well as during plant transients or AOOs. 

Operational limits will be established based 

on the proposed SLMCPR to ensure that the 

SLMCPR is not violated. This will ensure 

that the fuel design safety criterion (i.e., that 

at least 99.9% of the fuel rods do not 

experience transition boiling during normal 

operation and AOOs) is met. Since the 

proposed change does not affect operability 

of plant systems designed to mitigate any 

consequences of accidents, the consequences 

of an accident previously evaluated are not 

expected to increase. 

Therefore, the proposed change does not 

involve a significant increase in the 


rfrederick on PROD1PC67 with NOTICES