Federal Register / Vol. 74, No. 106 / Thursday, June 4, 2009 / Notices 26893 

Dated: June 1, 2009. 

Lynn Bryant, 

Department Clearance Officer, PRA, United 

States Department of Justice. 

[FR Doc. E9–13085 Filed 6–3–09; 8:45 am] 

BILLING CODE 4410–FY–P 

NEIGHBORHOOD REINVESTMENT 

CORPORATION 

Sunshine Act Meeting for the 31st 

Annual Board of Directors 

TIME AND DATE: 12:15 p.m., Wednesday, 

June 3, 2009. 

PLACE: 1325 G Street, NW., Suite 800, 

Boardroom, Washington, DC 20005. 

STATUS: Open. 

CONTACT PERSON FOR MORE INFORMATION: 

Erica Hall, Assistant Corporate 

Secretary; (202) 220–2376; 

ehall@nw.org. 

AGENDA: 

I. Call To Order. 

II. Approval of the Minutes. 

III. Summary Report of the Audit 

Committee. 

IV. Summary Report of the Corporate 

Administration Committee. 

V. Summary Report of the Finance, 

Budget and Program Committee. 

VI. Board Appointments. 

VII. Financial Report. 

VIII. Corporate Scorecard. 

IX. Chief Executive Officer’s Quarterly 

Management Report. 

X. Adjournment. 

Erica Hall, 

Assistant Corporate Secretary. 

[FR Doc. E9–13140 Filed 6–2–09; 11:15 am] 

BILLING CODE 7570–02–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 52–039–COL; ASLBP No. 09– 

890–10–COL–BD01] 

PPL Bell Bend, LLC, Bell Bend Nuclear 

Power Plant; 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 2.104, 2.300, 

2.313, 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: PPL Bell Bend, LLC, (Bell 

Bend Nuclear Power Plant). 

This proceeding concerns requests for 

hearing from petitioners Gene Stilp in 

his individual capacity; Gene Stilp for 

Taxpayers and Ratepayers United; and 

Eric Epstein in his individual capacity. 

The hearing requests were submitted in 

response to a March 18, 2009 Notice of 

Hearing, Opportunity to Petition for 

Leave to Intervene, and Associated 

Order (74 FR 11,606). Petitioners 

challenge the application filed by PPL 

Bell Bend, LLC pursuant to Subpart C of 

10 CFR part 52 for a combined license 

for the Bell Bend Nuclear Power Plant, 

to be located in Luzerne County, 

Pennsylvania. 

The Board is comprised of the 

following administrative judges: 

William J. Froehlich, Chair, Atomic 

Safety and Licensing Board Panel, 

U.S. Nuclear Regulatory Commission, 

Washington, DC 20555–0001; 

Michael F. Kennedy, Atomic Safety and 

Licensing Board Panel, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001; 

Randall J. Charbeneau, 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 28th 

day of May 2009. 

E. Roy Hawkens, 

Chief Administrative Judge, Atomic Safety 

and Licensing Board Panel. 

[FR Doc. E9–13022 Filed 6–3–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2008–0597] 

Notice of Issuance and Withdrawal of 

Regulatory Guides 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of Issuance and 

Availability of Regulatory Guide (RG) 

1.69, Revision 1 and withdrawal of RG 

2.1. 

FOR FURTHER INFORMATION CONTACT: 

Harriet Karagiannis, Regulatory Guide 

Development Branch, Division of 

Engineering, Office of Nuclear 

Regulatory Research, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001, telephone (301) 251– 

7477 or e-mail to 

Harriet.Karagiannis@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC) is issuing a revision 

to an existing guide in the agency’s 

‘‘Regulatory Guide’’ series. This series 

was developed to describe and make 

available to the public information such 

as methods that are acceptable to the 

NRC staff for implementing specific 

parts of the agency’s regulations, 

techniques that the staff uses in 

evaluating specific problems or 

postulated accidents, and data that the 

staff needs in its review of applications 

for permits and licenses. 

Revision 1 of RG 1.69, ‘‘Concrete 

Radiation Shields and Generic Shield 

Testing for Nuclear Power Plants,’’ was 

issued for public comment with a 

temporary identification as Draft 

Regulatory Guide (DG)–1187. RG 1.69 

describes a method acceptable to the 

NRC staff for complying with the 

regulations with regard to the design 

and construction of concrete radiation 

shields in nuclear power plants. 

As stated in Title 10, Section 20.1201, 

‘‘Occupational Dose Limits for Adults,’’ 

of the Code of Federal Regulations (10 

CFR 20.1201), NRC licensees shall 

control the occupational dose to 

individual adults to the limits stated 

therein. Furthermore, 10 CFR 20.1101(b) 

provides that licensees shall use, to the 

extent practicable, procedures and 

engineering controls based upon sound 

radiation principles to achieve 

occupational doses and doses to 

members of the public that are as low 

as reasonably achievable. General 

Design Criterion 1, ‘‘Quality Standards 

and Records,’’ of Appendix A, ‘‘General 

Design Criteria for Nuclear Power 

Plants,’’ to 10 CFR part 50, ‘‘Domestic 

Licensing of Production and Utilization 

Facilities,’’ requires that structures, 

systems, and components important to 

safety be designed, fabricated, erected, 

and tested to quality standards 

commensurate with the importance of 

the safety function to be performed. 

Appendix B, ‘‘Quality Assurance 

Criteria for Nuclear Power Plants and 

Fuel Reprocessing Plants,’’ to 10 CFR 

part 50 requires that measures be 

established to ensure design control and 

inspection and test controls. Appendix 

B also requires that activities affecting 

quality be accomplished under suitably 

controlled conditions. 

Also, RG 1.69 encompasses applicable 

material previously endorsed in RG 2.1, 

‘‘Shield Test Program for the Evaluation 

of Installed Biological Shielding in 

Research and Training Reactors.’’ 

Therefore, RG 2.1 is outdated and it will 

be withdrawn.