48102 Federal Register / Vol. 74, No. 181 / Monday, September 21, 2009 / Notices 

• Mail: Office of Information and 

Regulatory Affairs, Office of 

Management and Budget, Attn: Darcel 

D. Gayle, NEOB, Room 10202, 725 17th 

Street, NW., Washington, DC 20503. We 

are still experiencing delays in the 

regular mail, including first class and 

express mail. To ensure that your 

comments are received, we recommend 

that comments on this draft report be 

electronically submitted. 

All comments submitted in response 

to this notice will be made available to 

the public, including by posting them 

on OMB’s Web site. For this reason, 

please do not include in your comments 

information of a confidential nature, 

such as sensitive personal information 

or proprietary information. The http:// 

www.regulations.gov Web site is an 

‘‘anonymous access’’ system, which 

means OMB will not know your identity 

or contact information unless you 

provide it in the body of your comment. 

FOR FURTHER INFORMATION CONTACT: 

Darcel D. Gayle, Office of Information 

and Regulatory Affairs, Office of 

Management and Budget, NEOB, Room 

10202, 725 17th Street, NW., 

Washington, DC 20503. Telephone: 

(202) 395–3084. 

SUPPLEMENTARY INFORMATION: Congress 

directed the Office of Management and 

Budget (OMB) to prepare an annual 

Report to Congress on the Benefits and 

Costs of Federal Regulations. 

Specifically, section 624 of the FY 2001 

Treasury and General Government 

Appropriations Act, also known as the 

‘‘Regulatory Right-to-Know Act,’’ (the 

Act) requires OMB to submit a report on 

the benefits and costs of Federal 

regulations together with 

recommendation for reform. The Act 

states that the report should contain 

estimates of the benefits and costs of 

regulations in the aggregate, by agency 

and agency program, and by major rule, 

as well as an analysis of impacts of 

Federal regulation on State, local, and 

tribal governments, small businesses, 

wages, and economic growth. The Act 

also states that the report should go 

through notice and comment and peer 

review. 

Kevin F. Neyland, 

Deputy Administrator, Office of Information 

and Regulatory Affairs. 

[FR Doc. E9–22606 Filed 9–18–09; 8:45 am] 

BILLING CODE 3110–01–P 

NATIONAL SCIENCE FOUNDATION 

Advisory Committee for Geosciences; 

Notice of Meeting 

In accordance with the Federal 

Advisory Committee Act (Pub. L. 92– 

463, as amended), the National Science 

Foundation announces the following 

meeting: 

Name: Advisory Committee for 

Geosciences (1755). 

Dates: October 14, 2009, 8:15 a.m.–5:15 

p.m. 

October 15, 2009, 8:30 a.m.–2 p.m. 

Place: Stafford I, Room 1235, National 

Science Foundation, 4201 Wilson Blvd., 

Arlington, Virginia 22230. 

Type of Meeting: Open. 

Contact Person: Melissa Lane, National 

Science Foundation, Suite 705, 4201 Wilson 

Blvd., Arlington, Virginia 22230. Phone 703– 

292–8500. 

Minutes: May be obtained from the contact 

person listed above. 

Purpose of Meeting: To provide advice, 

recommendations, and oversight concerning 

support for research, education, and human 

resources development in the geosciences. 

Agenda: October 14: Directorate activities 

and plans, SODV Briefing, Division 

Subcommittee Meetings, Education & 

Diversity Subcommittee Meeting, Meeting 

with the Director and Deputy Director. 

October 15: Discussion of GEO 

International Activities, COV and 

Subcommittee Reports, Action Items/ 

Planning for Spring Meeting. 

Dated: September 16, 2009. 

Susanne Bolton, 

Committee Management Officer. 

[FR Doc. E9–22613 Filed 9–18–09; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0413] 

Draft Regulatory Guide: Issuance, 

Availability 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of Issuance and 

Availability of Draft Regulatory Guide, 

DG–1225. 

FOR FURTHER INFORMATION CONTACT: 

Jerome Bettle, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001, telephone: (301) 415–1314 or email to Jerome.Bettle@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC) is issuing for public 

comment a draft guide in the agency’s 

‘‘Regulatory Guide’’ series. This series 

was developed to describe and make 

available to the public such information 

as methods that are acceptable to the 

NRC staff for implementing specific 

parts of the NRC’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. 

The draft regulatory guide (DG), titled, 

‘‘Instrument Lines Penetrating the 

Primary Reactor Containment,’’ is 

temporarily identified by its task 

number, DG–1225, which should be 

mentioned in all related 

correspondence. DG–1225 is proposed 

Revision 1 of Regulatory Guide 1.11, 

dated March 1971. 

General Design Criterion (GDC) 55, 

‘‘Reactor Coolant Pressure Boundary 

Penetrating Containment,’’ and GDC 56, 

‘‘Primary Containment Isolation,’’ of 

Appendix A, ‘‘General Design Criteria 

for Nuclear Power Plants,’’ to Title 10, 

Part 50, ‘‘Domestic Licensing of 

Production and Utilization Facilities,’’ 

of the Code of Federal Regulations (10 

CFR Part 50) require, in part, that each 

line that penetrates the primary reactor 

containment and that is part of the 

reactor coolant pressure boundary or 

connects directly to the containment 

atmosphere has at least one locked, 

closed isolation valve or one automatic 

valve inside and one automatic valve 

outside containment ‘‘unless it can be 

demonstrated that the containment 

isolation provisions for a specific class 

of lines, such as instrument lines, are 

acceptable on some other defined 

basis.’’ This guide defines a basis that 

the staff of the NRC considers 

acceptable to implement GDC 55 and 56 

with regard to instrument lines. This 

guide applies to all types of nuclear 

power plants. 

II. Further Information 

The NRC staff is soliciting comments 

on DG–1225. Comments may be 

accompanied by relevant information or 

supporting data and should mention 

DG–1225 in the subject line. Comments 

submitted in writing or in electronic 

form will be made available to the 

public in their entirety through the 

NRC’s Agencywide Documents Access 

and Management System (ADAMS). 

Personal information will not be 

removed from your comments. You may 

submit comments by any of the 

following methods: 

1. Mail comments to: Rulemaking and 

Directives Branch, MS TWB 05 B01M, 

Office of Administration, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001. 

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Federal Register / Vol. 74, No. 181 / Monday, September 21, 2009 / Notices 48103 

2. E-mail comments to: 

nrcrep.resource@nrc.gov. 

3. Fax comments to: Rulemaking and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission at (301) 492–3446. 

Requests for technical information 

about DG–1225 may be directed to the 

NRC contact, Jerome Bettle at (301) 415– 

1314 or e-mail to Jerome.Bettle@nrc.gov. 

Comments would be most helpful if 

received by November 16, 2009. 

Comments received after that date will 

be considered if it is practical to do so, 

but the NRC is able to ensure 

consideration only for comments 

received on or before this date. 

Although a time limit is given, 

comments and suggestions in 

connection with items for inclusion in 

guides currently being developed or 

improvements in all published guides 

are encouraged at any time. 

Electronic copies of DG–1225 are 

available through the NRC’s public Web 

site under Draft Regulatory Guides in 

the ‘‘Regulatory Guides’’ collection of 

the NRC’s Electronic Reading Room at 

http://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also 

available in ADAMS (http:// 

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

under Accession No. ML090970530. 

In addition, regulatory guides are 

available for inspection at the NRC’s 

Public Document Room (PDR), which is 

located at 11555 Rockville Pike, 

Rockville, Maryland. The PDR’s mailing 

address is USNRC PDR, Washington, DC 

20555–0001. The PDR can also be 

reached by telephone at (301) 415–4737 

or (800) 397–4205, by fax at (301) 415– 

3548, and by e-mail to 

pdr.resource@nrc.gov. 

Regulatory guides are not 

copyrighted, and Commission approval 

is not required to reproduce them. 

Dated at Rockville, Maryland, this 14th day 

of September, 2009. 

For the Nuclear Regulatory Commission. 

Andrea D. Valentin, 

Chief, Regulatory Guide Development Branch, 

Division of Engineering, Office of Nuclear 

Regulatory Research. 

[FR Doc. E9–22601 Filed 9–18–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–298; NRC–2009–0398] 

Nebraska Public Power District; 

Cooper Nuclear Station; Exemption 

1.0 Background 

Nebraska Public Power District (NPPD 

or the licensee) is the holder of Facility 

Operating License No. DPR–46 which 

authorizes operation of the Cooper 

Nuclear Station (CNS). The license 

provides, among other things, that the 

facility is subject to the rules, 

regulations, and orders of the Nuclear 

Regulatory Commission (NRC, the 

Commission) now or hereafter in effect. 

The facility consists of a boiling-water 

reactor located in Nemaha County, 

Nebraska. 

2.0 Request/Action 

Title 10 of the Code of Federal 

Regulations (10 CFR), Part 50, paragraph 

50.54(o), requires primary reactor 

containments for water-cooled power 

reactors to be subject to the 

requirements of Appendix J to 10 CFR 

Part 50. Appendix J specifies the leakage 

test requirements, schedules, and 

acceptance criteria for tests of the leaktight integrity of the primary reactor 

containment and systems and 

components that penetrate the 

containment. Appendix J, Option B, 

‘‘Performance-Based Requirements,’’ 

Section III.A., ‘‘Type A Test,’’ requires, 

among other things, that the overall 

integrated leakage rate must not exceed 

the allowable leakage rate (La) with 

margin, as specified in the Technical 

Specifications (TSs). The overall 

integrated leakage rate is defined in 10 

CFR Part 50, Appendix J as ‘‘the total 

leakage rate through all tested leakage 

paths, including containment welds, 

valves, fittings, and components that 

penetrate the containment system.’’ This 

includes the contribution through the 

four main steam (MS) lines and the MS 

inboard drain line (penetration X–8). 

The MS Pathway includes leakage from 

the MS line penetrations plus the MS 

inboard drain line. 

Option B, Section III.B of 10 CFR Part 

50, Appendix J, ‘‘Type B and C Tests,’’ 

requires, among other things, that the 

sum of the leakage rates at accident 

pressure of Type B tests and pathway 

leakage rates from Type C tests be less 

than the performance criterion (La) with 

margin, as specified in the TSs. 

By application dated October 13, 

2008, as supplemented by letters dated 

April 8, May 29, June 12, and September 

1, 2009, the licensee requested 

exemption from Option B, Section III.A 

requirements in order to permit 

exclusion of MS Pathway leakage from 

the overall integrated leak rate test 

measurement. The licensee also 

requested exemption from Option B, 

Section III.B requirements in order to 

permit exclusion of the MS Pathway 

leakage contributions from the sum of 

the leakage rates from Type B and Type 

C tests. The licensee’s application 

included a license amendment request 

to revise the radiological assessment 

calculation methodology for the design 

basis loss-of-coolant accident at CNS 

through application of the alternative 

source term, in accordance with the 

provisions of 10 CFR 50.67 and 50.90, 

and to revise the TSs accordingly. 

The NRC previously granted a license 

amendment (Amendment No. 226, 

dated October 31, 2006) and an 

exemption (letter to licensee dated 

October 30, 2006) from (1) Option B, 

Section III.A requirements in order to 

permit exclusion of MS isolation valve 

(MSIV) leakage from the overall 

integrated leakage rate measured when 

performing a Type A test, and (2) 

Option B, Section III.B requirements in 

order to permit exclusion of the MSIV 

leakage from the combined leakage rate 

of the penetrations and valves subject to 

Type B and Type C tests. The only 

difference in the current exemption 

request is the inclusion of the leakage 

contribution from the MS inboard drain 

line with the MSIV leakage in the MS 

Pathway. 

The MS leakage effluent has a 

different pathway to the environment, 

when compared to a typical 

containment penetration. It is not 

directed into the secondary containment 

and filtered through the standby gas 

treatment system as is other 

containment leakage. Instead, the MS 

leakage is collected and treated via an 

alternative leakage treatment (ALT) path 

having different mitigation 

characteristics. 

In performing accident analyses, it is 

appropriate to group various leakage 

effluents according to the treatment they 

receive before being released to the 

environment (e.g., from MS pathways). 

The proposed exemption would more 

appropriately permit ALT pathway 

leakage to be independently grouped 

with its unique leakage limits. In this 

manner, the CNS containment leakage 

testing program will be more consistent 

with the limiting assumptions used in 

the associated accident consequence 

analyses. 

The licensee has analyzed the MS 

Pathway leakage separately from the 

overall containment integrated leakage, 

local leakage across pressure retaining, 

leakage limiting boundaries, and 

containment isolation valve leakage in 

its dose consequence analyses. 

Specifically, the alternative source term 

design-basis accident analyses use the 

MS piping, MS drain lines, and main 

condenser as an alternate means for MS 

Pathway leakage treatment. The dose 

consequences were found to be within 

the acceptance criteria of 10 CFR 50.67, 

‘‘Accident source term,’’ and the 

guidance of NRC Regulatory Guide 

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