33478 Federal Register / Vol. 74, No. 132 / Monday, July 13, 2009 / Notices 

Requirements (Design and 

Construction),’’ is temporarily identified 

by its task number, DG–1215, which 

should be mentioned in all related 

correspondence. DG–1215 is proposed 

Revision 4 of Regulatory Guide 1.28. 

DG–1215 describes methods that the 

NRC staff considers acceptable for 

complying with the provisions of 

Appendix B, ‘‘Quality Assurance 

Criteria for Nuclear Power Plants and 

Fuel Reprocessing Plants,’’ to Title 10, 

part 50, ‘‘Domestic Licensing of 

Production and Utilization Facilities,’’ 

of the Code of Federal Regulations (10 

CFR part 50) for establishing and 

implementing a quality assurance (QA) 

program for the design and construction 

of nuclear power plants, fuel fabrication 

plants and fuel reprocessing plants. 

The methods described in this 

revision are similar to the methods 

described in Regulatory Guide (RG) 

1.28, ‘‘Quality Assurance Program 

Requirements (Design and 

Construction),’’ Revision 3, which is the 

previously published version of this 

regulatory guide. RG 1.33, ‘‘Quality 

Assurance Program Requirements 

(Operation)’’ addresses additional 

guidance for the establishment and 

execution of QA programs for nuclear 

power plants during the operations 

phase, which is unaffected by the 

revision to RG 1.28. DG–1215 endorses 

methods defined in American Society of 

Mechanical Engineers (ASME) NQA–1, 

‘‘Quality Assurance Requirements for 

Nuclear Facility Applications.’’ The 

NRC is aware that the ASME standards 

committee has proposed minor changes 

to NQA–1 in a draft of ASME NQA–1a– 

2009, Addenda to ASME NQA–1–2008. 

If these addenda are issued in a timely 

manner, they will be considered for 

endorsement in RG 1.28, revision 4. 

II. Further Information 

The NRC staff is soliciting comments 

on DG–1215. Comments may be 

accompanied by relevant information or 

supporting data and should mention 

DG–1215 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, Office of 

Administration, MS TWB–05–B01M, 

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–2009–0308]. 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–1215 may be directed to the 

NRC contact, Paul Prescott at (301) 415– 

3026 or e-mail to Paul.Prescott@nrc.gov. 

Comments would be most helpful if 

received by September 8, 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–1215 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. ML090150402. 

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 6th day 

of July 2009. 

For the Nuclear Regulatory Commission. 

Mark P. Orr, 

Acting Chief, Regulatory Guide Development 

Branch, Division of Engineering, Office of 

Nuclear Regulatory Research. 

[FR Doc. E9–16494 Filed 7–10–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2008–0147] 

License Renewal Interim Staff 

Guidance LR–ISG–2008–01: Staff 

Guidance Regarding the Station 

Blackout Rule (10 CFR 50.63) 

Associated With License Renewal 

Applications; Notice of Withdrawal 

AGENCY: Nuclear Regulatory 

Commission (NRC). 

ACTION: Notice of withdrawal. 

SUMMARY: The NRC is withdrawing its 

proposed License Renewal Interim Staff 

Guidance (LR–ISG) LR–ISG–2008–01, 

‘‘Staff Guidance Regarding the Station 

Blackout Rule (10 CFR 50.63) 

Associated with License Renewal 

Applications.’’ The NRC staff issued the 

proposed guidance to clarify the 

acceptance criteria for the scoping of 

systems, structures, and components in 

accordance with section 54.4(a)(3) of 

Title 10 of the Code of Federal 

Regulations (10 CFR 54.4(a)(3)). 

However, after evaluating comments 

received on the proposed guidance, the 

NRC staff has determined that the 

current acceptance criteria, as provided 

in section 2.5.2.1.1 of NUREG–1800, 

Revision 1, ‘‘Standard Review Plan for 

Review of License Renewal 

Applications for Nuclear Power Plants’’ 

(SRP–LR), are adequate for the NRC 

staff’s review of license renewal 

applications. As such, the NRC staff is 

withdrawing the proposed LR–ISG– 

2008–01. 

On March 12, 2008, the NRC 

requested public comments on the 

proposed LR–ISG in the Federal 

Register (73 FR 13258). The proposed 

LR–ISG and accompanying figures are 

available in the NRC’s Agencywide 

Documents Access and Management 

System (ADAMS) under Accession Nos. 

ML080520619 and ML080520620, 

respectively. 

The NRC staff drafted the proposed 

LR–ISG–2008–01 after finding that some 

license renewal applications did not 

include within the scope of license 

renewal all structures and components 

required by 10 CFR 54.4(a)(3) for 

demonstrating compliance with 10 CFR 

50.63 (Station Blackout Rule). The 

proposed LR–ISG was intended to 

clarify the NRC staff’s acceptance 

criteria in SRP–LR section 2.5.2.1.1, 

‘‘Components Within the Scope of SBO 

(10 CFR 50.63).’’ 

By letters dated May 9, 2008 

(ML081400346), and May 12, 2008 

(ML081350619), the NRC received 

comments on the proposed LR–ISG from 

the Strategic Teaming and Resource 

mstockstill on DSKH9S0YB1PROD with NOTICES

Federal Register / Vol. 74, No. 132 / Monday, July 13, 2009 / Notices 33479 

Sharing alliance and the Nuclear Energy 

Institute (NEI), respectively. On July 18, 

2008, the NRC staff discussed these 

comments during a public meeting with 

NEI and industry representatives, as 

documented in ‘‘Summary of the 

License Renewal Meeting Held between 

the U.S. Nuclear Regulatory 

Commission Staff and the Nuclear 

Energy Institute,’’ dated October 3, 2008 

(ML082480547). Overall, the comments 

indicated that the NRC staff’s proposed 

guidance is too prescriptive and does 

not acknowledge the unique design 

aspects of each plant, as reflected in the 

plant’s current licensing basis. 

The NRC staff evaluated both the 

comments submitted in writing, and 

those provided during the July 18, 2008, 

meeting and subsequent public license 

renewal meetings, and determined that 

the proposed clarification in LR–ISG– 

2008–01 is unnecessary because the 

NRC staff’s review of license renewal 

applications is based on the plantspecific current licensing bases, 

regulatory requirements, and offsite 

power design configurations. As such, 

the NRC staff will continue to review 

license renewal applications against the 

acceptance criteria in SRP–LR section 

2.5.2.1.1 to ensure applicants include 

within the scope of license renewal the 

systems, structures, and components 

that perform functions to demonstrate 

compliance with the Station Blackout 

Rule, as required by 10 CFR 54.4(a)(3). 

Therefore, by this action, the NRC is 

withdrawing LR–ISG–2008–01. 

ADDRESSES: Documents created or 

received after November 1, 1999, are 

available electronically at the NRC’s 

Public Electronic Reading Room on the 

Internet at http://www.nrc.gov/readingrm/adams.html. From this site, the 

public can gain entry into ADAMS. If 

you do not have access to the Internet 

or if there are any problems in accessing 

the documents located in ADAMS, 

contact the NRC Public Document Room 

reference staff at 1–800–397–4209, 301– 

415–4737, or by e-mail at 

PDR.Resource@nrc.gov. 

FOR FURTHER INFORMATION CONTACT: Mr. 

Matthew Homiack, Division of License 

Renewal, Office of Nuclear Reactor 

Regulation, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555– 

0001; telephone 301–415–1683; or 

e-mail Matthew.Homiack@nrc.gov. 

SUPPLEMENTARY INFORMATION: The NRC 

issues LR–ISGs to communicate insights 

and lessons learned, and to address 

emergent issues not addressed in certain 

license renewal guidance documents. 

The NRC staff and stakeholders can use 

approved LR–ISGs until their guidance 

is incorporated into a formal license 

renewal guidance document revision. 

The NRC posts its issued LR–ISGs on 

the NRC Public Web page at http:// 

www.nrc.gov/reading-rm/doccollections/isg. 

Dated at Rockville, Maryland, this 7th day 

of July 2009. 

For the Nuclear Regulatory Commission. 

Brian E. Holian, 

Director, Division of License Renewal, Office 

of Nuclear Reactor Regulation. 

[FR Doc. E9–16486 Filed 7–10–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[NRC–2009–0117] 

Notice of Revised Regulatory Guide 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Notice of Revised Regulatory 

Guide (RG) 1.200, Revision 2, ‘‘An 

Approach for Determining the Technical 

Adequacy of Probabilistic Risk 

Assessment Results for Risk-Informed 

Activities.’’ 

FOR FURTHER INFORMATION CONTACT: 

Mary Drouin, Office of Nuclear 

Regulatory Research, U.S. Nuclear 

Regulatory Commission, Washington, 

DC 20555–0001, telephone (301) 251– 

7574 or e-mail to Mary.Drouin@nrc.gov. 

SUPPLEMENTARY INFORMATION: 

I. Introduction 

The Nuclear Regulatory Commission 

(NRC) issued Revision 2 of RG 1.200 on 

March 17, 2009, which was published 

in the Federal Register, 74 FR 11381. 

RG 1.200, Revision 2 is a 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. 

A sentence was inadvertently omitted 

from the draft version that was issued 

for public comment and the final 

version that was published in March 

2009. The current version of Regulatory 

Guide 1.200 on the NRC Web site 

includes the omitted sentence at the end 

of the first paragraph in Regulatory 

Position C.1.2.5. 

II. Further Information 

Electronic copies of Regulatory Guide 

1.200, Revision 2 are available through 

the NRC’s public Web site under 

‘‘Regulatory Guides’’ at http:// 

www.nrc.gov/reading-rm/doccollections/. In addition, regulatory 

guides are available for inspection at the 

NRC’s Public Document Room (PDR) 

located at Room O–1F21, One White 

Flint North, 11555 Rockville Pike, 

Rockville, Maryland 20852–2738. 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) 397–4209, by 

fax at (301) 415–3548, and by e-mail to 

pdr.resource@nrc.gov. 

Regulatory guides are not 

copyrighted, and NRC approval is not 

required to reproduce them. 

Dated at Rockville, Maryland, this 2nd day 

of July 2009. 

For the Nuclear Regulatory Commission. 

Mark P. Orr, 

Acting Chief, Regulatory Guide Development 

Branch, Division of Engineering, Office of 

Nuclear Regulatory Research. 

[FR Doc. E9–16499 Filed 7–10–09; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket Nos. 50–254 and 50–265; NRC– 

2009–0309] 

Exelon Generation Company, LLC; 

Notice of Withdrawal of Application for 

Amendment to Facility Operating 

License 

The U.S. Nuclear Regulatory 

Commission (the Commission) has 

granted the request of Exelon 

Generation Company, LLC (the licensee) 

to withdraw its December 21, 2007, 

application for proposed amendment to 

Renewed Facility Operating License 

Nos. DPR–29 and DPR–30 for the Quad 

Cities Nuclear Power Station, Units 1 

and 2, located in Rock Island County, 

Illinois. 

The proposed amendment would 

have revised the Technical 

Specifications Surveillance 

Requirements to establish an acceptance 

criterion to verify that total battery 

connector resistances for the 125 and 

250 volt direct current batteries are 

within pre-established limits that ensure 

the batteries can perform their design 

function. 

The Commission had previously 

issued a Notice of Consideration of 

Issuance of Amendment published in 

the Federal Register on February 26, 

2008 (73 FR 10298) and December 30, 

2008 (73 FR 79932). However, by letter 

dated June 25, 2009, the licensee 

withdrew the proposed change. 

mstockstill on DSKH9S0YB1PROD with NOTICES