[Federal Register Volume 75, Number 72 (Thursday, April 15, 2010)]
[Page 19665]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 2010-8650]




Final Regulatory Guide: Issuance, Availability

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Issuance and Availability of Regulatory Guide (RG) 
1.65, Revision 1, ``Materials and Inspections for Reactor Vessel 
Closure Studs.''


Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 251-
7650 or e-mail [email protected].


I. Introduction

    The U.S. Nuclear Regulatory Commission (NRC) is issuing 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.
    RG 1.65, Revision 1, ``Materials and Inspections for Reactor Vessel 
Closure Studs,'' was issued with a temporary identification as Draft 
Regulatory Guide, DG-1211. General Design Criterion (GDC) 1, ``Quality 
Standards and Records,'' of Appendix A, ``General Design Criteria for 
Nuclear Power Plants,'' to Title 10, of the Code of Federal 
Regulations, part 50, ``Domestic Licensing of Production and 
Utilization Facilities'' (10 CFR part 50), requires, in part, that 
``[s]tructures, systems, and components important to safety shall be 
designed, fabricated, erected, and tested to quality standards 
commensurate with the importance of the safety function to be 
performed. Where generally recognized codes and standards are used, 
they shall be identified and evaluated to determine their 
applicability, adequacy, and sufficiency and shall be supplemented or 
modified as necessary to ensure a quality product in keeping with the 
required safety function.''
    GDC 30, ``Quality of Reactor Coolant Pressure Boundary,'' requires, 
in part, that ``[c]omponents that are part of the reactor coolant 
pressure boundary shall be designed, fabricated, erected, and tested to 
the highest practical quality standards.''
    GDC 31, ``Fracture Prevention of Reactor Coolant Pressure 
Boundary,'' requires, in part, that ``[t]he reactor coolant pressure 
boundary shall be designed with sufficient margin to assure that when 
stressed under operating, maintenance, testing, and postulated accident 
conditions (1) the boundary behaves in a nonbrittle manner and (2) the 
probability of rapidly propagating fracture is minimized.''
    Appendix B, ``Quality Assurance Criteria for Nuclear Power Plants 
and Fuel Reprocessing Plants,'' to 10 CFR part 50 requires, in part, 
that ``[m]easures be established to assure that special processes, 
including welding, heat treating, and nondestructive testing, are 
controlled and accomplished by qualified personnel using qualified 
procedures in accordance with applicable codes, standards, 
specifications, criteria, and other special requirements.''

II. Further Information

    In April 2009, DG-1211 was issued for public comment. The public 
comment period closed on June 12, 2009. The staff's responses to the 
public comments received are located in the NRC's Agencywide Documents 
Access and Management System under Accession Number ML092050752. 
Electronic copies of RG 1.65, Revision 1 are available through the 
NRC's public Web site under ``Regulatory Guides'' at http://www.nrc.gov/reading-rm/doc-collections/.
    In addition, regulatory guides are available for inspection at the 
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 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 [email protected].
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

    Dated at Rockville, Maryland, this 8 day of April, 2010.

    For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch, Division of Engineering, 
Office of Nuclear Regulatory Research.
[FR Doc. 2010-8650 Filed 4-14-10; 8:45 am]