56938 Federal Register / Vol. 70, No. 188 / Thursday, September 29, 2005 / Notices 

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. Eric A. Thornsbury 

(telephone (301) 415–8716), five days 

prior to the meeting, if possible, so that 

appropriate arrangements can be made. 

Electronic recordings will be permitted. 

Further information regarding this 

meeting can be obtained by contacting 

the Designated Federal Official or the 

Cognizant Staff Engineer between 7:30 

a.m. and 4:15 p.m. (ET). Persons 

planning to attend this meeting are 

urged to contact one of the above named 

individuals at least two working days 

prior to the meeting to be advised of any 

potential changes to the agenda. 

Dated: September 21, 2005. 

Michael R. Snodderly, 

Acting Chief, ACRS/ACNW. 

[FR Doc. E5–5318 Filed 9–28–05; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Final Regulatory Guide: Issuance, 

Availability 

The U.S. Nuclear Regulatory 

Commission (NRC) has issued a revision 

to an existing guide in the agency’s 

Regulatory Guide Series. This series has 

been 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. 

Revision 33 of Regulatory Guide 1.84, 

‘‘Design, Fabrication, and Materials 

Code Case Acceptability, ASME Section 

III,’’ lists the NRC-approved Code Cases 

from Section III, ‘‘Rules for Construction 

of Nuclear Power Plant Components,’’ of 

the Boiler and Pressure Vessel (BPV) 

Code promulgated by the American 

Society of Mechanical Engineers 

(ASME). In so doing, this guide 

identifies the Code Cases that nuclear 

power plant applicants and licensees 

can use to comply with the NRC’s 

requirements in Title 10, Section 

50.55a(c), of the Code of Federal 

Regulations [10 CFR 50.55a(c)], ‘‘Reactor 

Coolant Pressure Boundary.’’

Specifically, 10 CFR 50.55a(c) requires, 

in part, that components of the reactor 

coolant pressure boundary must be 

designed, fabricated, erected, and tested 

in accordance with the ASME Section 

III requirements for Class 1 components 

(or equivalent quality standards). The 

ASME publishes a new edition of the 

BPV Code (which includes Section III) 

every 3 years, new addenda every year, 

and Code Cases every quarter. 

Revision 33 of Regulatory Guide 1.84 

identifies the Code Cases that the NRC 

has determined to be acceptable 

alternatives to applicable provisions of 

Section III. For this revision, the NRC 

staff reviewed Section III Code Cases 

listed in Supplement 12 to the 1998 

Edition of the ASME BPV Code through 

Supplement 6 to the 2001 Edition. 

The newly approved Code Cases and 

revisions to existing Code Cases will be 

incorporated by reference into 10 CFR 

50.55a(b), which identifies the latest 

editions and addenda of Section III that 

the NRC has approved for use. Code 

Cases approved by the NRC may be used 

voluntarily by licensees as an 

alternative to compliance with ASME 

Code provisions that have been 

incorporated by reference into 10 CFR 

50.55a(b). Section III Code Cases not yet 

endorsed by the NRC may be 

implemented through 10 CFR 

50.55a(a)(3), which 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 their use is authorized by the 

Director of the NRC’s Office of Nuclear 

Reactor Regulation. 

On August 3, 2004, the NRC staff 

published a draft of this guide as Draft 

Regulatory Guide DG–1124. Following 

the closure of the public comment 

period on September 2, 2004, the staff 

considered all stakeholder comments in 

the course of preparing Revision 33 of 

Regulatory Guide 1.84. 

The NRC staff encourages and 

welcomes comments and suggestions in 

connection with improvements to 

published regulatory guides, as well as 

items for inclusion in regulatory guides 

that are currently being developed. You 

may submit comments by any of the 

following methods. 

Mail comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555–

0001. 

Hand-deliver comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, 11555 Rockville Pike, 

Rockville, Maryland 20852, between 

7:30 a.m. and 4:15 p.m. on Federal 

workdays. 

Fax comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission at (301) 415–5144. 

Requests for technical information 

about Revision 33 of Regulatory Guide 

1.84 may be directed to Wallace E. 

Norris, at (301) 415–6796 or 

WEN@nrc.gov. 

Regulatory guides are available for 

inspection or downloading through the 

NRC’s public Web site in the Regulatory 

Guides document collection of the 

NRC’s Electronic Reading Room at 

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

Revision 33 of Regulatory Guide 1.84 

are also available in the NRC’s 

Agencywide Documents Access and 

Management System (ADAMS) at 

http://www.nrc.gov/reading-rm/ 

adams.html, under Accession 

#ML052130562. Note, however, that the 

NRC has temporarily suspended public 

access to ADAMS so that the agency can 

complete security reviews of publicly 

available documents and remove 

potentially sensitive information. Please 

check the NRC’s Web site for updates 

concerning the resumption of public 

access to ADAMS. 

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 email to PDR@nrc.gov. 

Requests for single copies of draft or 

final guides (which may be reproduced) 

or for placement on an automatic 

distribution list for single copies of 

future draft guides in specific divisions 

should be made in writing to the U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, Attention: 

Reproduction and Distribution Services 

Section; by email to 

DISTRIBUTION@nrc.gov; or by fax to 

(301) 415–2289. Telephone requests 

cannot be accommodated. 

Regulatory guides are not 

copyrighted, and Commission approval 

is not required to reproduce them. 

(5 U.S.C. 552(a)) 

Dated at Rockville, Maryland, this 15th day 

of August, 2005. 

Federal Register / Vol. 70, No. 188 / Thursday, September 29, 2005 / Notices 56939 

For the U.S. Nuclear Regulatory 

Commission, 

Carl J. Paperiello, 

Director, Office of Nuclear Regulatory 

Research. 

[FR Doc. 05–19444 Filed 9–28–05; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Final Regulatory Guide: Issuance, 

Availability 

The U.S. Nuclear Regulatory 

Commission (NRC) has issued a revision 

to an existing guide in the agency’s 

Regulatory Guide Series. This series has 

been 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. 

Revision 1 of Regulatory Guide 1.193, 

‘‘ASME Code Cases Not Approved for 

Use,’’ lists the Code Cases that the NRC 

has determined are not acceptable for 

generic use as specified in Section III, 

‘‘Rules for Construction of Nuclear 

Power Plant Components,’’ and Section 

XI, ‘‘Rules for Inservice Inspection of 

Nuclear Power Plant Components,’’ of 

the Boiler and Pressure Vessel (BPV) 

Code promulgated by the American 

Society of Mechanical Engineers 

(ASME). (In so doing, this guide 

complements Revision 33 of Regulatory 

Guide 1.84, ‘‘Design, Fabrication, and 

Materials Code Case Acceptability, 

ASME Section III,’’ and Revision 14 of 

Regulatory Guide 1.147, ‘‘Inservice 

Inspection Code Case Acceptability, 

ASME Section XI, Division 1,’’ which 

list the Code Cases that the NRC has 

determined to be acceptable alternatives 

to applicable provisions of Section III 

and Section XI, respectively.) 

Licensees may request NRC approval 

to implement one or more of the Code 

Cases listed in Revision 1 of Regulatory 

Guide 1.193, as provided in 10 CFR 

50.55a(a)(3), which 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. 

To do so, a licensee must submit a 

plant-specific request that addresses the 

NRC’s concern about the given Code 

Case. 

On August 3, 2004, the NRC staff 

published a draft of this guide as Draft 

Regulatory Guide DG–1126. Following 

the closure of the public comment 

period on September 2, 2004, the staff 

considered all stakeholder comments in 

the course of preparing Revision 1 of 

Regulatory Guide 1.193. 

The NRC staff encourages and 

welcomes comments and suggestions in 

connection with improvements to 

published regulatory guides, as well as 

items for inclusion in regulatory guides 

that are currently being developed. You 

may submit comments by any of the 

following methods. 

Mail comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555–

0001. 

Hand-deliver comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission, 11555 Rockville Pike, 

Rockville, Maryland 20852, between 

7:30 a.m. and 4:15 p.m. on Federal 

workdays. 

Fax comments to: Rules and 

Directives Branch, Office of 

Administration, U.S. Nuclear Regulatory 

Commission at (301) 415–5144. 

Requests for technical information 

about Revision 1 of Regulatory Guide 

1.193 may be directed to Wallace E. 

Norris, at (301) 415–6796 or 

WEN@nrc.gov. 

Regulatory guides are available for 

inspection or downloading through the 

NRC’s public Web site in the Regulatory 

Guides document collection of the 

NRC’s Electronic Reading Room at 

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

Revision 1 of Regulatory Guide 1.193 

are also available in the NRC’s 

Agencywide Documents Access and 

Management System (ADAMS) at http:// 

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

under Accession #ML052140501. Note, 

however, that the NRC has temporarily 

suspended public access to ADAMS so 

that the agency can complete security 

reviews of publicly available documents 

and remove potentially sensitive 

information. Please check the NRC’s 

Web site for updates concerning the 

resumption of public access to ADAMS. 

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@nrc.gov. 

Requests for single copies of draft or 

final guides (which may be reproduced) 

or for placement on an automatic 

distribution list for single copies of 

future draft guides in specific divisions 

should be made in writing to the U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, Attention: 

Reproduction and Distribution Services 

Section; by e-mail to 

DISTRIBUTION@nrc.gov; or by fax to 

(301) 415–2289. Telephone requests 

cannot be accommodated. 

Regulatory guides are not 

copyrighted, and Commission approval 

is not required to reproduce them. 

(5 U.S.C. 552(a)) 

Dated at Rockville, Maryland, this 15th day 

of August, 2005. 

For the U.S. Nuclear Regulatory 

Commission. 

Carl J. Paperiello, 

Director, Office of Nuclear Regulatory 

Research. 

[FR Doc. 05–19445 Filed 9–28–05; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

Final Regulatory Guide: Issuance, 

Availability 

The U.S. Nuclear Regulatory 

Commission (NRC) has issued a revision 

to an existing guide in the agency’s 

Regulatory Guide Series. This series has 

been 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. 

Revision 14 of Regulatory Guide 

1.147, ‘‘Inservice Inspection Code Case 

Acceptability, ASME Section XI, 

Division 1,’’ lists the NRC-approved 

Code Cases from Section XI, ‘‘Rules for 

Inservice Inspection of Nuclear Power 

Plant Components,’’ of the Boiler and 

Pressure Vessel (BPV) Code 

promulgated by the American Society of 

Mechanical Engineers (ASME). In so 

doing, this guide identifies the Code 

Cases that nuclear power plant 

applicants and licensees can use to 

comply with the NRC’s requirements in 

Title 10, Section 50.55a(g), of the Code 

of Federal Regulations [10 CFR 

50.55a(g)], ‘‘Inservice Inspection 

Requirements.’’ Specifically, 10 CFR 

50.55a(g) requires, in part, that Class 1, 

2, 3, MC, and CC components and their 

supports must meet the requirements of 

ASME Section XI (or equivalent quality 

standards). The ASME publishes a new 

edition of the BPV Code (which 

includes Section XI) every 3 years, new