52426 Federal Register / Vol. 73, No. 175 / Tuesday, September 9, 2008 / Notices 

depositing the document with the 

provider of the service. 

Non-timely requests and/or petitions 

and contentions will not be entertained 

absent a determination by the 

Commission, the presiding officer, or 

the Atomic Safety and Licensing Board 

that the petition and/or request should 

be granted and/or the contentions 

should be admitted, based on a 

balancing of the factors specified in 10 

CFR 2.309(c)(1)(i)–(viii). To be timely, 

filings must be submitted no later than 

11:59 p.m. Eastern Time on the due 

date. 

Documents submitted in adjudicatory 

proceedings will appear in NRC’s 

electronic hearing docket which is 

available to the public at http:// 

ehd.nrc.gov/EHD_Proceeding/home.asp, 

unless excluded pursuant to an order of 

the Commission, an Atomic Safety and 

Licensing Board, or a Presiding Officer. 

Participants are requested not to include 

personal privacy information, such as 

social security numbers, home 

addresses, or home phone numbers in 

their filings. With respect to copyrighted 

works, except for limited excerpts that 

serve the purpose of the adjudicatory 

filings and would constitute a Fair Use 

application, participants are requested 

not to include copyrighted materials in 

their submission. 

Exelon Generation Company, LLC, 

Docket No. 50–249, Dresden Nuclear 

Power Station, Unit 3, Grundy County, 

Illinois 

Date of amendment request: August 

18, 2008. 

Description of amendment request: 

The amendment revises Technical 

Specification 3.4.5, ‘‘RCS Leakage 

Detection Instrumentation,’’ to support 

implementation of an alternative 

method of verifying that unidentified 

leakage in the drywell is within limits. 

Date of issuance: August 22, 2008. 

Effective date: As of the date of 

issuance and shall be implemented by 

12:00 pm CDT on August 24, 2008. 

Amendment No.: 221. 

Facility Operating License No. DPR–

25: Amendment revises the technical 

specifications and the operating license. 

Public comments requested as to 

proposed no significant hazards 

consideration (NSHC): 

No. On August 17, 2008, the staff 

issued a Notice of Enforcement 

Discretion, which was effective 

immediately and remained in effect 

until this amendment was issued. 

The Commission’s related evaluation 

of the amendment, finding of emergency 

circumstances, state consultation, and 

final NSHC determination are contained 

in a safety evaluation dated August 22, 

2008. 

Attorney for licensee: Mr. Bradley J. 

Fewell, Associate General Counsel, 

Exelon Generation. 

NRC Branch Chief: Russell Gibbs. 

Dated at Rockville, Maryland, this 29th day 

of August 2008. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. E8–20567 Filed 9–8–08; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–282–LR, 50–306–LR; 

ASLBP No. 08–871–01–LR–BD01] 

Nuclear Management Company, LLC; 

Establishment of Atomic Safety and 

Licensing Board 

Pursuant to delegation by the 

Commission dated December 29, 1972, 

published in the Federal Register, 37 FR 

28,710 (1972), and the Commission’s 

regulations, see 10 CFR 104, 2.300, 

2.303, 2.309, 2.311, 2.318, and 2.321, 

notice is hereby given that an Atomic 

Safety and Licensing Board (Board) is 

being established to preside over the 

following proceeding: 

Nuclear Management Company, LLC 

(Prairie Island Nuclear Generating 

Plant, Units 1 and 2) 

This proceeding involves an 

application for renewal of the licenses 

that authorize Nuclear Management 

Company, LLC to operate Prairie Island 

Nuclear Generating Plant, Units 1 and 2 

for a twenty-year period beyond their 

current expiration dates of, respectively, 

August 9, 2013 and October 29, 2014. In 

response to a June 17, 2008 Notice of 

Acceptance for Docketing of the 

Application and Notice of Opportunity 

for Hearing (73 FR 34,335), a petition to 

intervene has been submitted by Philip 

R. Mahowald on behalf of the Prairie 

Island Indian Community. 

The Board is comprised of the 

following administrative judges: 

William J. Froehlich, Chairman, Atomic 

Safety and Licensing Board Panel, 

U.S. Nuclear Regulatory Commission, 

Washington, DC 20555–0001 

Gary S. Arnold, Atomic Safety and 

Licensing Board Panel, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001 

Thomas J. Hirons, Atomic Safety and 

Licensing Board Panel, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001 

All correspondence, documents, and 

other materials shall be filed in 

accordance with the NRC E-Filing rule, 

which the NRC promulgated in August 

2007 (72 FR 49,139). 

Issued at Rockville, Maryland, this 3rd day 

of September 2008. 

E. Roy Hawkens, 

Chief Administrative Judge, Atomic Safety 

and Licensing Board Panel. 

[FR Doc. E8–20849 Filed 9–8–08; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–243; EA–08–251] 

In the Matter of: Oregon State 

University (Oregon State University 

TRIGA Reactor); Order Modifying 

Facility Operating License No. R–106 

I 

Oregon State University (the licensee) 

is the holder of Facility Operating 

License No. R–106 (the license), issued 

by the U.S. Nuclear Regulatory 

Commission (NRC). The NRC plans to 

renew the license on September 10, 

2008. The license authorizes operation 

of the Oregon State University TRIGA 

Reactor (the facility) at a power level up 

to 1,100 kilowatts thermal and in the 

pulse mode, with reactivity insertions 

not to exceed $2.55, and to receive, 

possess, and use special nuclear 

material associated with facility 

operation. The facility is a research 

reactor located on the campus of Oregon 

State University, in the city of Corvallis, 

Benton County, Oregon. The mailing 

address is Radiation Center, Oregon 

State University, 100 Radiation Center, 

Corvallis, Oregon 97331–5903. 

II 

Title 10 of the Code of Federal 

Regulations (10 CFR) Section 50.64, 

limits the use of high-enriched uranium 

(HEU) fuel in domestic non-power 

reactors (research and test reactors) (see 

51 FR 6514). The regulation, which 

became effective on March 27, 1986, 

requires that if Federal Government 

funding for conversion-related costs is 

available, each licensee of a non-power 

reactor authorized to use HEU fuel shall 

replace it with low-enriched uranium 

(LEU) fuel acceptable to the 

Commission unless the Commission has 

determined that the reactor has a unique 

purpose. The Commission’s stated 

purpose for these requirements was to 

reduce, to the maximum extent possible, 

the use of HEU fuel in order to reduce 

the risk of theft and diversion of HEU 

fuel used in non-power reactors. 


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