26440 Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Notices 

documents electronically must file a 

motion, in accordance with 10 CFR 

2.302(g), with their initial paper filing 

requesting authorization to continue to 

submit documents in paper format. 

Such filings must be submitted by: (1) 

First class mail addressed to the Office 

of the Secretary of the Commission, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, Attention: 

Rulemaking and Adjudications Staff; or 

(2) courier, express mail, or expedited 

delivery service to the Office of the 

Secretary, Sixteenth Floor, One White 

Flint North, 11555 Rockville Pike, 

Rockville, Maryland 20852, Attention: 

Rulemaking and Adjudications Staff. 

Participants filing a document in this 

manner are responsible for serving the 

document on all other participants. 

Filing is considered complete by firstclass mail as of the time of deposit in 

the mail, or by courier, express mail, or 

expedited delivery service upon 

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. 

Virginia Electric and Power Company, 

Docket No. 50–280, Surry Power Station, 

Unit No. 1, Surry County, Virginia 

Date of amendment request: May 5, 

2009, as supplemented by letter dated 

May 6, 2009. 

Brief Description of amendments: 

This amendment revised Technical 

Specifications (TSs) 6.4.Q, ‘‘Steam 

Generator (SG) Program,’’ and TS 6.6.3, 

‘‘Steam Generator Tube Inspection 

Report,’’ to modify the interim alternate 

repair criteria for SG B tube repair to 

allow tubes with a permeability 

variation in the lowest one inch of the 

tube sheet to remain in service during 

Refueling Outage 22 (spring 2009) and 

the subsequent operating cycle. The 

amendment also revised reporting 

requirement TS 6.6.A.3, ‘‘SG Tube 

Inspection Report.’’ 

Date of issuance: May 7, 2009. 

Effective date: As of the date of 

issuance and shall be implemented 

within 30 days. 

Amendment No.: 264. 

Facility Operating License No. DPR– 

32: Amendment revises the license and 

TSs. 

Public comments requested as to 

proposed no significant hazards 

consideration (NSHC): No. 

The Commission’s related evaluation 

of the amendment, finding of emergency 

circumstances, state consultation, and 

final no significant hazards 

consideration determination are 

contained in a safety evaluation dated 

May 7, 2009. 

Attorney for licensee: Lillian M. 

Cuoco, Esq., Senior Counsel, Dominion 

Resources Services, Inc.,120 Tredegar 

St., RS–2, Richmond, VA 23219. 

NRC Branch Chief: Melanie C. Wong. 

Dated at Rockville, Maryland, this 21st day 

May 2009. 

For the Nuclear Regulatory Commission. 

Joseph G. Giitter, 

Director, Division of Operating Reactor 

Licensing, Office of Nuclear Reactor 

Regulation. 

[FR Doc. E9–12511 Filed 6–1–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0014] 

Draft Regulatory Guides: Issuance, 

Availability 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of issuance and 

availability of Draft Regulatory Guides 

DG–1191, DG–1192, and DG–1193. 

FOR FURTHER INFORMATION CONTACT: 

Wallace E. Norris, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001, telephone: (301) 251– 

7650 or e-mail to 

Wallace.Norris@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The U.S. Nuclear Regulatory 

Commission (NRC) is issuing for public 

comment three Draft Regulatory Guides 

(DGs) in the agency’s ‘‘Regulatory 

Guide’’ series. Specifically, these are 

Revision 35 of Regulatory Guide (RG) 

1.84, ‘‘Design, Fabrication, and 

Materials Code Case Acceptability, 

ASME Section III’’ (temporarily 

identified by its task number, DG–1191); 

Revision 16 of RG 1.147, ‘‘Inservice 

Inspection Code Case Acceptability, 

ASME Section XI, Division 1’’ 

(temporarily identified by its task 

number DG–1192); and Revision 3 of RG 

1.193, ‘‘ASME Code Cases Not 

Approved for Use’’ (temporarily 

identified by its task number DG–1193). 

This series was developed to describe 

and make available to the public such 

information as methods acceptable to 

the NRC staff for implementing specific 

parts of NRC’s regulations, techniques 

the staff uses in evaluating specific 

problems or postulated accidents, and 

data the staff needs in its review of 

applications for permits and licenses. 

II. Discussion 

Regulatory Guide 1.84 (temporarily 

identified by its task number, DG–1191) 

lists all Section III Code Cases that NRC 

has approved for use. For Revision 35 of 

the guide, NRC reviewed the Section III 

Code Cases listed in Supplements 2–11 

to the 2004 Edition of the American 

Society of Mechanical Engineers 

(ASME) Boiler and Pressure Vessel 

(BPV) Code and Supplement 0 to the 

2007 Edition (Supplement 0 also serves 

as Supplement 12 to the 2004 Edition). 

Appendix A to this guide lists the 

supplements reviewed, the applicable 

edition, and the date on which each 

supplement was approved by the ASME 

Board on Nuclear Codes and Standards. 

Appendix B is a list of the Section III 

Code Cases addressed in the eleven 

supplements. Finally, Appendix C is a 

current list of all Section III Code Cases. 

Provisions of the ASME BPV Code 

have been used since 1971 as one part 

of the framework to establish the 

necessary design, fabrication, 

construction, testing, and performance 

requirements for structures, systems, 

and components important to safety. 

Among other things, ASME standards 

committees develop improved methods 

for the construction and inservice 

inspection (ISI) of ASME Classes 1, 2, 3, 

MC (metal containment), and CC 

(concrete containment) nuclear power 

plant components. A broad spectrum of 

stakeholders participate in the ASME 

process, which helps to ensure that the 

various interests are considered. 

The regulation in Title 10, Part 50, of 

the Code of Federal Regulations (CFR), 

10 CFR 50.55a(c), ‘‘Reactor Coolant 

Pressure Boundary,’’ requires, in part, 

Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Notices 26441 

that components of the reactor coolant 

pressure boundary must be designed, 

fabricated, erected, and tested in 

accordance with the requirements for 

Class 1 components of Section III, 

‘‘Rules for Construction of Nuclear 

Power Plant Components,’’ of the ASME 

BPV Code or equivalent quality 

standards. ASME publishes a new 

edition of the BPV Code, which 

includes Section III, every 3 years and 

new addenda every year. The latest 

editions and addenda of Section III that 

NRC has approved for use are 

referenced in 10 CFR 50.55a(b). 

ASME also publishes Code Cases 

quarterly. Code Cases provide 

alternatives developed and approved by 

ASME. This RG identifies the Code 

Cases that have been determined by 

NRC to be acceptable alternatives to 

applicable parts of Section III. Section 

III Code Cases not yet endorsed by NRC 

may be used by a licensee or applicant 

through 10 CFR 50.55a(a)(3). That 

section permits the use of alternatives to 

the Code requirements referenced in 10 

CFR 50.55a provided that the proposed 

alternatives result in an acceptable level 

of quality and safety and that their use 

is authorized by the Director of the 

Office of Nuclear Reactor Regulation. 

The ASME Code is incorporated by 

reference into 10 CFR 50.55a. Code 

Cases approved by NRC provide an 

acceptable voluntary alternative to the 

mandatory ASME Code provisions. 

Therefore, NRC will amend 10 CFR 

50.55a to incorporate by reference the 

new Code Cases and revisions to 

existing Code Cases listed in this guide 

and to state the requirements governing 

the use of Code Cases. Because of 

continuing change in the status of Code 

Cases, the staff plans periodic updates 

to 10 CFR 50.55a and this guide to 

accommodate new Code Cases and any 

revisions of existing Code Cases. 

For Revision 16 of RG 1.147 

(temporarily identified by its task 

number DG–1192), NRC reviewed the 

Section XI Code Cases listed in 

Supplements 2 through 11 to the 2004 

Edition and Supplement 0 published 

with the 2007 Edition (Supplement 0 

also serves as Supplement 12 to the 

2004 Edition) of the ASME BPV Code. 

Appendix A to this guide lists the 

supplements reviewed, the edition, the 

supplement number, and the date on 

which the supplement was approved by 

the ASME Board on Nuclear Codes and 

Standards. Appendix B is a list of the 

Section XI Code Cases published by 

ASME in the 11 supplements. Finally, 

Appendix C is a current list of all 

Section XI Code Cases. 

The regulation in 10 CFR 50.55a(g), 

‘‘Inservice Inspection Requirements,’’ 

requires, in part, that Classes 1, 2, 3, 

metal containment (MC) and concrete 

containment (CC) components and their 

supports meet the requirements of 

Section XI, ‘‘Rules for Inservice 

Inspection of Nuclear Power Plant 

Components,’’ of the ASME BPV Code 

or equivalent quality standards. Every 3 

years, ASME publishes a new edition of 

the BPV Code, including Section XI, and 

new addenda are published every year. 

The latest editions and addenda of 

Section XI that NRC has approved for 

use are referenced in 10 CFR 50.55a(b). 

ASME also publishes Code Cases 

quarterly. Code Cases provide 

alternatives to existing Code 

requirements that ASME developed and 

approved. This RG identifies the Code 

Cases that NRC has determined to be 

acceptable alternatives to applicable 

parts of Section XI. Licensees may use 

these Code Cases without requesting 

authorization from NRC provided they 

are used with any identified limitations 

or modifications. Section XI Code Cases 

not yet endorsed by NRC may be used 

by a licensee or applicant through 10 

CFR 50.55a(a)(3). That section permits 

the use of alternatives to the Code 

requirements referenced in 10 CFR 

50.55a provided the proposed 

alternatives result in an acceptable level 

of quality and safety and that their use 

is authorized by the Director of the 

Office of Nuclear Reactor Regulation. 

The ASME Code is incorporated by 

reference into 10 CFR 50.55a, which 

NRC will amend to incorporate this 

guide by reference; 10 CFR 50.55a states 

the requirements governing the use of 

Code Cases. Because of continuing 

change in the status of Code Cases, the 

staff plans periodic updates to 10 CFR 

50.55a and this guide to accommodate 

new Code Cases and any revisions of 

existing Code Cases. Code Cases 

approved by NRC provide an acceptable 

voluntary alternative to the mandatory 

ASME Code provisions. 

Revision 3 of RG 1.193 (temporarily 

identified by its task number DG–1193) 

lists the Code Cases that NRC has 

determined not to be acceptable for use 

on a generic basis. A brief description of 

the basis for the determination is 

provided with each Code Case. 

Licensees may submit a request to 

implement one or more of the Code 

Cases listed through 10 CFR 

50.55a(a)(3), which permits the use of 

alternatives to the Code requirements 

referenced in 10 CFR 50.55a, provided 

the proposed alternatives result in an 

acceptable level of quality and safety. 

Licensees must submit a plant-specific 

request that addresses NRC’s concerns 

about the Code Case at issue. 

In 10 CFR Part 50 ‘‘Domestic 

Licensing of Production and Utilization 

Facilities,’’ Section 50.55a(c), ‘‘Reactor 

Coolant Pressure Boundary,’’ requires, 

in part, that components of the reactor 

coolant pressure boundary be designed, 

fabricated, erected, and tested in 

accordance with the requirements for 

Class 1 components of Section III, 

‘‘Rules for Construction of Nuclear 

Power Plant Components,’’ of the ASME 

BPV Code or equivalent quality 

standards. Section 50.55a(f), ‘‘Inservice 

Testing Requirements,’’ requires, in 

part, that Classes 1, 2, and 3 

components and their supports meet the 

requirements of the ASME Code for 

Operation and Maintenance of Nuclear 

Power Plants (OM Code) or equivalent 

quality standards. Finally, 10 CFR 

50.55a(g), ‘‘Inservice Inspection 

Requirements,’’ requires, in part, that 

Classes 1, 2, 3, MC and CC components 

and their supports meet the 

requirements of Section XI, ‘‘Rules for 

Inservice Inspection of Nuclear Power 

Plant Components,’’ of the ASME BPV 

Code or equivalent quality standards. 

III. Further Information 

The NRC staff is soliciting comments 

on DG–1191, DG–1192, and DG–1193. 

Comments may be accompanied by 

relevant information or supporting data 

and should mention DG–1191, DG– 

1192, or DG–1193 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, Mail Stop: TWB–05– 

B01M, Office of Administration, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001. 

2. Federal e-Rulemaking Portal: Go to 

http://www.regulations.gov and search 

for documents filed under Docket ID 

[NRC–2009–0014]. Address questions 

about NRC dockets to Carol Gallagher 

301–492–3668; e-mail 

Carol.Gallagher@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–1191, DG–1192, and DG–1193 

may be directed to the NRC contact, 

Wallace E. Norris, at (301) 251–7650 or 

e-mail to Wallace.Norris@nrc.gov. 

Comments would be most helpful if 

received by August 17, 2009. Comments 

26442 Federal Register / Vol. 74, No. 104 / Tuesday, June 2, 2009 / Notices 

received after that date will be 

considered if it is practical to do so, but 

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–1191, DG– 

1192, and DG–1193 are available 

through NRC’s public Web site under 

Draft Regulatory Guides in the 

‘‘Regulatory Guides’’ collection of NRC’s 

Electronic Reading Room at http:// 

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

available in ADAMS (http:// 

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

under Accession No. ML080910389 

(DG–1191), ML080910245 (DG–1192), 

and ML080920854 (DG–1193). 

In addition, regulatory guides are 

available for inspection at NRC’s Public 

Document Room (PDR) located at 11555 

Rockville Pike, Rockville, Maryland. 

The PDR’s mailing address is USNRC 

PDR, Washington, DC 20555–0001. The 

PDR also can 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 21st day 

of May 2009. 

For the Nuclear Regulatory Commission. 

James E. Lyons, 

Deputy Director, Office of Nuclear Regulatory 

Research. 

[FR Doc. E9–12750 Filed 6–1–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Advisory Committee on Reactor 

Safeguards; Amendment to June 3–5, 

2009, ACRS Meeting—Federal Register 

Notice 

The Federal Register Notice for the 

ACRS meeting scheduled to be held on 

June 3–5, 2009, is being amended to 

notify the following: 

In accordance with Subsection 10(d) 

Public Law 92–463, it may be necessary 

to close portions of the meeting to 

discuss and protect information 

classified as proprietary to Mitsubishi 

Heavy Industries and its contractors 

pursuant to 5 U.S.C. 552b (c) (4). 

The notice of this meeting was 

previously published in the Federal 

Register on Monday, May 18, 2009 [74 

FR 23222–23224]. All other items 

remain the same as previously 

published. 

Further information regarding this 

meeting can be obtained by contacting 

Girija Shukla, Cognizant ACRS staff 

(301–415–6855), between 7:15 a.m. and 

5 p.m., (ET). 

Dated: May 27, 2009. 

Andrew L. Bates, 

Advisory Committee Management Officer. 

[FR Doc. E9–12753 Filed 6–1–09; 8:45 am] 

BILLING CODE 7590–01–P 

OFFICE OF PERSONNEL 

MANAGEMENT 

[OMB Control No. 3206–0138; Form RI 30– 

9] 

Proposed Collection; Request for 

Extension of a Currently Approved 

Information Collection 

AGENCY: Office of Personnel 

Management. 

ACTION: Notice. 

SUMMARY: In accordance with the 

Paperwork Reduction Act of 1995 (Pub. 

L. 104–13, May 22, 1995), this notice 

announces that the Office of Personnel 

Management (OPM) intends to submit to 

the Office of Management and Budget 

(OMB) a request for extension of a 

currently approved information 

collection. This information collection, 

‘‘Reinstatement of Disability Annuity 

Previously Terminated Because of 

Restoration to Earning Capacity’’ (OMB 

Control No. 3206–0138; Form RI 30–9), 

informs former disability annuitants of 

their right to request restoration under 

title 5, U.S.C. Section 8337. It also 

specifies the conditions to be met and 

the documentation required for a person 

to request reinstatement. 

Comments are particularly invited on: 

Whether this collection of information 

is necessary for the proper performance 

of functions of the Office of Personnel 

Management, and whether it will have 

practical utility; whether our estimate of 

the public burden of this collection of 

information is accurate, and based on 

valid assumptions and methodology; 

and ways in which we can minimize the 

burden of the collection of information 

on those who are to respond, through 

the use of appropriate technological 

collection techniques or other forms of 

information technology. 

Approximately 200 forms are 

completed annually. The form takes 

approximately 60 minutes to respond, 

including a medical examination. The 

annual estimated burden is 200 hours. 

Burden may vary depending on the time 

required for a medical examination. 

For copies of this proposal, contact 

Cyrus S. Benson on (202) 606–4808, 

FAX (202) 606–0910 or via E-mail to 

Cyrus.Benson@opm.gov. Please include 

a mailing address with your request. 

DATES: Comments on this proposal 

should be received within 60 calendar 

days from the date of this publication. 

ADDRESSES: Send or deliver comments 

to—James K. Freiert, Deputy Assistant 

Director, Retirement Services Program, 

Center for Retirement and Insurance 

Services, U.S. Office of Personnel 

Management, 1900 E Street, NW., Room 

3305, Washington, DC 20415–3500. 

For information regarding 

administrative coordination contact: 

Cyrus S. Benson, Team Leader, 

Publications Team, RIS Support 

Services/Support Group, U.S. Office of 

Personnel Management, 1900 E Street, 

NW., Room 4H28, Washington, DC 

20415, (202) 606–0623. 

U.S. Office of Personnel Management. 

John Berry, 

Director. 

[FR Doc. E9–12812 Filed 6–1–09; 8:45 am] 

BILLING CODE 6325–38–P 

OFFICE OF PERSONNEL 

MANAGEMENT 

[OMB Control No. 3206–0134; Standard 

Form 2803 and Standard Form 3108] 

Proposed Collection; Request for 

Comments Review of an Existing 

Information Collection 

AGENCY: Office of Personnel 

Management. 

ACTION: Notice. 

SUMMARY: In accordance with the 

Paperwork Reduction Act of 1995 (Pub. 

L. 10413, May 22, 1995), this notice 

announces that the Office of Personnel 

Management (OPM) intends to submit to 

the Office of Management and Budget 

(OMB) a request for review of an 

existing information collection. 

‘‘Application to Make Deposit or 

Redeposit (CSRS)’’ (OMB Control No. 

3206–0134; Standard Form 2803) and 

‘‘Application to Make Service Credit 

Payment for Civilian Service (FERS)’’ 

(OMB Control No. 3206–0134; Standard 

Form 3108) are applications to make 

payment used by persons who are 

eligible to pay for Federal service which 

was not subject to retirement deductions 

and/or for Federal service which was 

subject to retirement deductions which 

were subsequently refunded to the 

applicant. 

Comments are particularly invited on: 

Whether this collection of information 

is necessary for the proper performance