7632 Federal Register / Vol. 75, No. 34 / Monday, February 22, 2010 / Notices 

Need for the Proposed Action 

The licensee has ceased conducting 

license activities at the Facility, and 

seeks the unrestricted use of the 

Facility. 

Environmental Impacts of the Proposed 

Actions 

The licensee’s historical review of 

past research activities determined that 

Hydrogen-3 was the only radionuclide 

used in the Facility. The final status 

survey of the Facility was performed 

during September 2009. The final status 

survey results were attached to the 

Licensee’s amendment request dated 

September 29, 2009 (ML092730395). 

The NRC evaluated the licensee’s 

compliance with the radiological 

criteria for unrestricted use as specified 

in 10 CFR 20.1402 by using the 

screening approach described in 

NUREG–1757, ‘‘Consolidated 

Decommissioning Guidance,’’ Volume 1. 

The NRC NUREG specifies 

radionuclide-specific Derived 

Concentration Guideline Levels 

(DCGLs), developed by the NRC, which 

comply with the dose criterion in 10 

CFR 20.1402. The DCGLs define the 

maximum amount of residual 

radioactivity on surfaces that will satisfy 

the NRC requirements in Subpart E of 

10 CFR Part 20 for unrestricted use. The 

Licensee’s final status survey results 

were well below these DCGLs and are in 

compliance with the As Low as 

Reasonably Achievable (ALARA) 

requirement of 10 CFR 20.1402. The 

NRC thus finds that the Licensee’s final 

status survey results are acceptable. 

Based on its review, the staff has 

determined that the affected 

environment and any environmental 

impacts associated with the proposed 

action are bounded by the impacts 

evaluated by the ‘‘Generic 

Environmental Impact Statement in 

Support of Rulemaking on Radiological 

Criteria for License Termination of NRCLicensed Nuclear Facilities’’ (NUREG– 

1496) Volumes 1–3 (ML042310492, 

ML042320379, and ML042330385). The 

staff finds there were no significant 

environmental impacts from the use of 

radioactive material at the Facility. 

The NRC staff reviewed the docket 

file records and the final status survey 

report to identify any non-radiological 

hazards that may have impacted the 

environment surrounding the Facility. 

No such hazards or impacts to the 

environment were identified. The NRC 

has identified no other radiological or 

non-radiological activities in the area 

that could result in cumulative 

environmental impacts. 

The NRC staff finds that the proposed 

release of the Facility for unrestricted 

use is in compliance with 10 CFR 

20.1402. Based on its review, the staff 

considered the impact of the residual 

radioactivity at the Facility and 

concluded that the proposed action will 

not have a significant effect on the 

quality of the environment. 

Environmental Impacts of the 

Alternatives to the Proposed Action 

Due to the largely administrative 

nature of the proposed action, its 

environmental impacts are small. 

Therefore, the only alternative the staff 

considered is the no-action alternative, 

under which the staff would leave 

things as they are by simply denying the 

amendment request. This no-action 

alternative is not feasible because it 

conflicts with 10 CFR 30.36(d) requiring 

that decommissioning of byproduct 

material facilities be completed and 

approved by the NRC after licensed 

activities cease. The NRC’s analysis of 

the licensee’s final status survey data 

confirmed that the Facility meets the 

requirements of 10 CFR 20.1402 for 

unrestricted use. Additionally, denying 

the amendment request would result in 

no change in current environmental 

impacts. The environmental impacts of 

the proposed action and the no-action 

alternative are therefore similar, and the 

no-action alternative is accordingly not 

further considered. 

Agencies and Persons Consulted 

NRC provided a draft of this 

Environmental Assessment to the 

Illinois Emergency Management Agency 

(IEMA) for review on December 28, 

2009. IEMA had no comments or 

questions. 

Conclusion 

The NRC staff has concluded that the 

proposed action is consistent with the 

NRC’s unrestricted use criteria specified 

in 10 CFR 20.1402. Because the 

proposed action will not significantly 

impact the quality of the human 

environment, the NRC staff concludes 

that the proposed action is the preferred 

alternative. 

III. Finding of No Significant Impact 

The NRC staff has prepared this EA in 

support of the proposed action. On the 

basis of this EA, the NRC finds that 

there are no significant environmental 

impacts from the proposed action, and 

that preparation of an environmental 

impact statement is not warranted. 

Accordingly, the NRC has determined 

that a Finding of No Significant Impact 

is appropriate. 

IV. Further Information 

Documents related to this action, 

including the application for license 

amendment and supporting 

documentation, are available 

electronically at the NRC’s Electronic 

Reading Room at http://www.nrc.gov/ 

reading-rm/adams.html. From this site, 

you can access the NRC’s image files of 

NRC’s public documents. If you do not 

have access to ADAMS, or if there are 

problems in accessing the documents 

located in ADAMS, contact the NRC 

Public Document Room (PDR) Reference 

staff at 1–800–397–4209, 301–415–4737, 

or by e-mail to pdr.resource@nrc.gov. 

The documents related to this action are 

listed below, along with their ADAMS 

accession numbers. 

1. Department of the Army License 

Termination Request dated September 

29, 2009 (ADAMS Accession No. 

ML092730395). 

2. Title 10 Code of Federal 

Regulations, Part 20, Subpart E, 

‘‘Radiological Criteria for License 

Termination.’’ 

3. Title 10 Code of Federal 

Regulations, Part 51, ‘‘Environmental 

Protection Regulations for Domestic 

licensing and Related Regulatory 

Function.’’ 

3. NUREG–1757, Consolidated 

Decommissioning Guidance. 

These documents may also be viewed 

electronically on the public computers 

located at the NRC’s PDR, O1F21, One 

White Flint North, 11555 Rockville 

Pike, Rockville, MD 20852. The PDR 

reproduction contractor will copy 

documents for a fee. 

Dated at Lisle, Illinois, this 11th day of 

February 2010. 

For the Nuclear Regulatory Commission. 

Christine A. Lipa, 

Chief, Materials Control, ISFSI, and 

Decommissioning Branch, Division of Nuclear 

Materials Safety, Region III. 

[FR Doc. 2010–3353 Filed 2–19–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS) Meeting of the 

Subcommittee on Advanced Boiling 

Water Reactor (ABWR) 

The ACRS Subcommittee on ABWR 

will hold a meeting on March 2, 2010, 

at 11545 Rockville Pike, Rockville, 

Maryland, Room T2 B3. 

The meeting will be open to public 

attendance, with the exception of a 

portion that may be closed to protect 

information that is proprietary to South 


cprice-sewell on DSK2BSOYB1PROD with NOTICES
Federal Register / Vol. 75, No. 34 / Monday, February 22, 2010 / Notices 7633 

Texas Project (STP), pursuant to 5 

U.S.C. 552b(c)(4). 

The agenda for the subject meeting 

shall be as follows: 

March 2, 2010, 8:30 a.m.–5 p.m. 

The Subcommittee will review 

selected chapters (1, 4, 11, 12, 15 and 

18) of the Safety Evaluation Report with 

Open Items associated with the STP 

Combined License Application. The 

Subcommittee will gather information, 

analyze relevant issues and facts, and 

formulate proposed positions and 

actions, as appropriate, for deliberation 

by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), Maitri Banerjee 

(Telephone: 301–415–6973, E-mail: 

Maitri.Banerjee@nrc.gov) five days prior 

to the meeting, if possible, so that 

appropriate arrangements can be made. 

Thirty-five hard copies of each 

presentation or handout should be 

provided to the DFO thirty minutes 

before the meeting. In addition, one 

electronic copy of each presentation 

should be e-mailed to the DFO one day 

before the meeting. If an electronic copy 

cannot be provided within this 

timeframe, presenters should provide 

the DFO with a CD containing each 

presentation at least thirty minutes 

before the meeting. Electronic 

recordings will be permitted only 

during those portions of the meeting 

that are open to the public. Detailed 

procedures for the conduct of and 

participation in ACRS meetings were 

published in the Federal Register on 

October 14, 2009 (74 FR 58268–58269). 

Detailed meeting agendas and meeting 

transcripts are available on the NRC 

Web site at http://www.nrc.gov/readingrm/doc-collections/acrs. Information 

regarding topics to be discussed, 

changes to the agenda, whether the 

meeting has been canceled or 

rescheduled, and the time allotted to 

present oral statements can be obtained 

from the Web site cited above or by 

contacting the identified DFO. 

Moreover, in view of the possibility that 

the schedule for ACRS meetings may be 

adjusted by the Chairman as necessary 

to facilitate the conduct of the meeting, 

persons planning to attend should check 

with these references if such 

rescheduling would result in major 

inconvenience. 

Dated: February 12, 2010. 

Antonio F. Dias, 

Chief Reactor Safety Branch B, Advisory 

Committee on Reactor Safeguards. 

[FR Doc. 2010–3348 Filed 2–19–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS); Meeting of the 

ACRS Subcommittee on EPR; Notice 

of Meeting 

The ACRS U.S. Evolutionary Power 

Reactor (EPR) Subcommittee will hold a 

meeting on March 3, 2010, at 11545 

Rockville Pike, T2–B3, Rockville, 

Maryland. 

The entire meeting will be open to 

public attendance, with the exception of 

a portion that may be closed to protect 

information that is proprietary to 

AREVA NP, pursuant to 5 U.S.C. 

552b(c)(4). 

The proposed agenda for the subject 

meeting shall be as follows: 

Wednesday, March 3, 2010—8:30 

a.m.–5 p.m. 

The Subcommittee will review 

selected chapters (Chapters 4 and 5) of 

the Safety Evaluation Report with Open 

Items associated with the U.S. EPR 

Design Certification Document Review. 

The Subcommittee will gather 

information, analyze relevant issues and 

facts, and formulate proposed positions 

and actions, as appropriate, for 

deliberation by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), Mr. Derek 

Widmayer (Telephone 301–415–7366, 

E-mail: Derek.Widmayer@nrc.gov) five 

days prior to the meeting, if possible, so 

that appropriate arrangements can be 

made. Thirty-five hard copies of each 

presentation or handout should be 

provided to the DFO thirty minutes 

before the meeting. In addition, one 

electronic copy of each presentation 

should be e-mailed to the DFO one day 

before the meeting. If an electronic copy 

cannot be provided within this 

timeframe, presenters should provide 

the DFO with a CD containing each 

presentation at least thirty minutes 

before the meeting. Electronic 

recordings will be permitted. Detailed 

procedures for the conduct of and 

participation in ACRS meetings were 

published in the Federal Register on 

October 14, 2009 (74 FR 58268–58269). 

Detailed meeting agendas and meeting 

transcripts are available on the NRC 

Web site at http://www.nrc.gov/ 

reading-rm/doc-collections/acrs. 

Information regarding topics to be 

discussed, changes to the agenda, 

whether the meeting has been canceled 

or rescheduled, and the time allotted to 

present oral statements can be obtained 

from the Web site cited above or by 

contacting the identified DFO. 

Moreover, in view of the possibility that 

the schedule for ACRS meetings may be 

adjusted by the Chairman as necessary 

to facilitate the conduct of the meeting, 

persons planning to attend should check 

with these references if such 

rescheduling would result in major 

inconvenience. 

Dated: February 12, 2010. 

Antonio F. Dias, 

Chief, Reactor Safety Branch B, Advisory 

Committee on Reactor Safeguards. 

[FR Doc. 2010–3345 Filed 2–19–10; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS); Meeting of the 

Subcommittee on Plant Operations 

and Fire Protection; Notice of Meeting 

The ACRS Subcommittee on Plant 

Operations and Fire Protection will hold 

a meeting on March 3, 2010, at 11545 

Rockville Pike, Rockville, Maryland, 

Room T2 B1. 

The entire meeting will be open to 

public attendance. 

The agenda for the subject meeting 

shall be as follows: 

March 3, 2010—3 p.m.–5 p.m. 

The Subcommittee will review the 

status of the Watts Bar Unit 2 Operating 

License Application review. The 

Subcommittee will gather information, 

analyze relevant issues and facts, and 

formulate proposed positions and 

actions, as appropriate, for deliberation 

by the Full Committee. 

Members of the public desiring to 

provide oral statements and/or written 

comments should notify the Designated 

Federal Official (DFO), Maitri Banerjee 

(Telephone: 301–415–6973, E-mail: 

Maitri.Banerjee@nrc.gov) five days prior 

to the meeting, if possible, so that 

appropriate arrangements can be made. 

Thirty-five hard copies of each 

presentation or handout should be 

provided to the DFO thirty minutes 

before the meeting. In addition, one 

electronic copy of each presentation 

should be emailed to the DFO one day 

before the meeting. If an electronic copy 

cannot be provided within this 

timeframe, presenters should provide 

the DFO with a CD containing each 

presentation at least thirty minutes 

before the meeting. Electronic 

recordings will be permitted only 

during those portions of the meeting 

that are open to the public. Detailed 

procedures for the conduct of and 

participation in ACRS meetings were 

published in the Federal Register 

October 14, 2009 (74 FR 58268–58269). 


cprice-sewell on DSK2BSOYB1PROD with NOTICES