Federal Register / Vol. 74, No. 49 / Monday, March 16, 2009 / Notices 11137 

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 and the termination of the NRC 

materials license 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 human environment. The 

NRC thus finds that the Licensee’s final 

status survey results are acceptable to 

support free release of the Facility for 

unrestricted use and for termination of 

the NRC license. 

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 40.42(d), 

requiring that decommissioning of 

source 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 release and for license 

termination. 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. 

Conclusion 

The NRC staff has concluded that the 

proposed action is consistent with the 

NRC’s unrestricted release 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. 

Agencies and Persons Consulted 

NRC provided a draft of this 

Environmental Assessment to the 

Connecticut Department of 

Environmental Protection for review on 

January 22, 2009. On February 17, 2009, 

the Connecticut Department of 

Environmental Protection responded. 

The Connecticut Department of 

Environmental Protection agreed with 

the conclusions of the EA and otherwise 

had no comments. 

The NRC staff has determined that the 

proposed action is of a procedural 

nature and will not affect listed species 

or critical habitat. Therefore, no further 

consultation is required under Section 7 

of the Endangered Species Act. The 

NRC staff has also determined that the 

proposed action is not the type of 

activity that has the potential to cause 

effects on historic properties. Therefore, 

no further consultation is required 

under Section 106 of the National 

Historic Preservation Act. 

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 Agencywide 

Document Access and Management 

System (ADAMS), which provides text 

and image files of NRC’s public 

documents. The documents related to 

this action are listed below, along with 

their ADAMS accession numbers. 

1. Letter from Alpha Q to NRC dated 

April 21, 2008, submitting a proposed 

final site status survey plan 

(ML081350674); 

2. Letter from NRC to Alpha Q dated 

June 19, 2008, approving a modification 

to the default DCGLs and requesting 

additional information regarding the 

proposed final survey plan 

(ML081710745); 

3. Letter from Alpha Q to NRC dated 

June 30, 2008, providing additional 

information regarding the proposed 

final status survey plan (ML082000589); 

4. Letter from NRC to Alpha Q 

approving final survey plan, dated July 

11, 2008 (ML081960062); 

5. Letter from Alpha Q to NRC 

submitting final survey results and 

requesting license termination, dated 

November 20, 2008 (ML083330496); 

6. NRC Inspection Record dated 

January 9, 2009 (ML090200015); 

7. NUREG–1757, ‘‘Consolidated 

NMSS Decommissioning Guidance;’’ 

8. Title 10 Code of Federal 

Regulations, Part 20, Subpart E, 

‘‘Radiological Criteria for License 

Termination;’’ 

9. Title 10, Code of Federal 

Regulations, Part 51, ‘‘Environmental 

Protection Regulations for Domestic 

Licensing and Related Regulatory 

Functions;’’ and 

10. NUREG–1496, ‘‘Generic 

Environmental Impact Statement in 

Support of Rulemaking on Radiological 

Criteria for License Termination of NRCLicensed Nuclear Facilities.’’ 

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@nrc.gov. 

These documents may also be viewed 

electronically on the public computers 

located at the NRC’s PDR, O 1 F21, One 

White Flint North, 11555 Rockville 

Pike, Rockville, MD 20852. The PDR 

reproduction contractor will copy 

documents for a fee. 

Dated at Region I, 475 Allendale Road, 

King of Prussia, PA this 6th day of March 

2009. 

For the Nuclear Regulatory Commission. 

James P. Dwyer, 

Chief, Commercial and R&D Branch, Division 

of Nuclear Materials Safety, Region I. 

[FR Doc. E9–5601 Filed 3–13–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0110] 

Interim Staff Guidance on Disposition 

of Review of Evaluation To Address 

Adverse Flow Effects in Equipment 

Other Than Reactor Internals 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Solicitation of public comment. 

SUMMARY: The NRC is soliciting public 

comment on its Proposed Interim Staff 

Guidance (ISG) DC/COL–ISG–010 

(Agencywide Documents Access and 

Management System (ADAMS) 

11138 Federal Register / Vol. 74, No. 49 / Monday, March 16, 2009 / Notices 

Accession No. ML090510728). The 

purpose of this ISG is to modify and 

provide additional clarity in the 

guidance for the review of analyses of 

adverse flow effects in equipment other 

than reactor internals performed by 

Combined License (COL) and Design 

Certification (DC) applicants. This ISG 

would revise the staff guidance 

previously issued in March 2007 in the 

Standard Review Plan (SRP) NUREG– 

0080, ‘‘Standard Review Plan for the 

Review of Safety Analysis Reports for 

Nuclear Power Plants,’’ Section 3.9.2, 

‘‘Dynamic Testing and Analysis of 

Systems, Structures, and Components,’’ 

Section 3.9.5, ‘‘Reactor Pressure Vessel 

Internals,’’ and Regulatory Guide 1.20, 

‘‘Comprehensive Vibration Assessment 

Program for Reactor Internals During 

Pre-operational and Initial Startup 

Testing.’’ The NRC staff issues DC/COL– 

ISGs to facilitate timely implementation 

of current staff guidance and to facilitate 

activities associated with review of 

applications for DCs and COLs by the 

Office of New Reactors. The NRC staff 

will also incorporate the approved DC/ 

COL–ISG–010 into the next revision of 

the SRP and related guidance 

documents. 

DATES: Comments must be filed no later 

than 30 days from the date of 

publication of this notice in the Federal 

Register. Comments received after this 

date will be considered, if it is practical 

to do so, but the Commission is able to 

ensure consideration only for comments 

received on or before this date. 

ADDRESSES: Comments may be 

submitted to: Chief, Rulemaking, 

Directives, and Editing Branch, Office of 

Administration, Mail Stop TWB–05– 

B01M, U.S. Nuclear Regulatory 

Commission, Washington, DC, 20555– 

0001, and should cite the publication 

date and page number of the Federal 

Register notice. 

The NRC ADAMS provides text and 

image files of NRC’s public documents. 

These documents may be accessed 

through the NRC’s Public Electronic 

Reading Room on the Internet at http:// 

www.nrc.gov/reading-rm/adams.html. 

Persons who do not have access to 

ADAMS or who encounter problems in 

accessing the documents located in 

ADAMS should contact the NRC Public 

Document Room reference staff at 1– 

800–397–4209, 301–415–4737, or by email at PDR.Resource@nrc.gov. 

FOR FURTHER INFORMATION CONTACT: Ms. 

Jennifer L. Dixon-Herrity, Chief, 

Engineering Mechanics Branch 2, 

Division of Engineering, Office of the 

New Reactors, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001; telephone 301–415–2967 or e-mail 

at jennifer.dixon-herrity@nrc.gov. 

SUPPLEMENTARY INFORMATION: The 

agency posts its issued staff guidance in 

the agency external Web page (http:// 

www.nrc.gov/reading-rm/doccollections/isg/). The NRC staff is 

issuing this notice to solicit public 

comments on proposed DC/COL–ISG– 

010. After the NRC staff considers any 

public comments, it will make a 

determination regarding proposed DC/ 

COL–ISG–010. 

Dated at Rockville, Maryland, this 9th day 

of March 2009. 

For the Nuclear Regulatory Commission. 

William F. Burton, 

Branch Chief, Rulemaking and Guidance 

Development Branch, Division of New Reactor 

Licensing, Office of New Reactors. 

[FR Doc. E9–5604 Filed 3–13–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS) Meeting of the 

Subcommittee on Plant License 

Renewal; Notice of Meeting 

The ACRS Subcommittee on Plant 

License Renewal will hold a meeting on 

April 1, 2009, Room T–2B3, 11545 

Rockville Pike, Rockville, Maryland. 

The entire meeting will be open to 

public attendance. 

The agenda for the subject meeting 

shall be as follows: 

Wednesday, April 1, 2009–8:30 a.m.– 

12:30 p.m. 

The Subcommittee will discuss the 

license renewal application for the 

Susquehanna Steam Electric Station, 

Units 1 and 2 and the associated Safety 

Evaluation Report (SER) with Open 

Items prepared by the staff. The 

Subcommittee will hear presentations 

by and hold discussions with 

representatives of the NRC staff, PPL 

Susquehanna, and other interested 

persons regarding this matter. 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, Mr. Peter Wen 

(telephone (301) 415–2832 five days 

prior to the meeting, if possible, so that 

appropriate arrangements can be made. 

Electronic recordings will be permitted. 

Detailed procedures for the conduct of 

and participation in ACRS meetings 

were published in the Federal Register 

on October 6, 2008 (73 FR 58268– 

58269). 

Further information regarding this 

meeting can be obtained by contacting 

the Designated Federal Official between 

6:45 a.m. and 3:30 p.m. (ET). Persons 

planning to attend this meeting are 

urged to contact the above named 

individual at least two working days 

prior to the meeting to be advised of any 

potential changes to the agenda. 

Dated: March 10, 2009. 

Cayetano Santos, 

Chief, Reactor Safety Branch A, Advisory 

Committee on Reactor Safeguards. 

[FR Doc. E9–5600 Filed 3–13–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards (ACRS); Subcommittee 

Meeting on Planning and Procedures 

Notice of Meeting 

The ACRS Subcommittee on Planning 

and Procedures will hold a meeting on 

April 1, 2009, Room T2–B1, 11545 

Rockville Pike, Rockville, Maryland. 

The entire meeting will be open to 

public attendance, with the exception of 

a portion that may be closed pursuant 

to 5 U.S.C. 552b(c)(2) and (6) to discuss 

organizational and personnel matters 

that relate solely to the internal 

personnel rules and practices of the 

ACRS, and information the release of 

which would constitute a clearly 

unwarranted invasion of personal 

privacy. 

The agenda for the subject meeting 

shall be as follows: 

Wednesday, April 1, 2009, 12 p.m.–1 

p.m. 

The Subcommittee will discuss 

proposed ACRS activities and related 

matters. 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 Officer, Mr. Sam Duraiswamy 

(Telephone: 301–415–7364) between 

7:30 a.m. and 4 p.m. (ET) five days prior 

to the meeting, if possible, so that 

appropriate arrangements can be made. 

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 6, 2008 (73 FR 58268– 

58269).