[Federal Register Volume 74, Number 127 (Monday, July 6, 2009)]
[Notices]
[Page 31992]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E9-15787]


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NUCLEAR REGULATORY COMMISSION

[NRC-2009-0277]


Draft Regulatory Guide: Issuance, Availability

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of issuance and availability of Draft Regulatory Guide, 
DG-1224.

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FOR FURTHER INFORMATION CONTACT: Jeffrey Hixon, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, telephone: (301) 251-7639 or e-
mail to <a href="/cdn-cgi/l/email-protection#09436c6f6f7b6c7027416071666749677b6a276e667f"><span class="__cf_email__" data-cfemail="84cee1e2e2f6e1fdaaccedfcebeac4eaf6e7aae3ebf2">[email protected]</span></a>.

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), entitled, ``Control of the 
Processing and Use of Stainless Steel,'' is temporarily identified by 
its task number, DG-1224, which should be mentioned in all related 
correspondence. DG-1224 is proposed Revision 1 of Regulatory Guide 
1.44, dated May 1973.
    General Design Criterion 1, ``Quality Standards and Records,'' and 
Criterion 4, ``Environmental and Dynamic Effects Design Bases,'' 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 that components be designed, fabricated, erected, and tested to 
quality standards commensurate with the importance of the safety 
functions to be performed and that they be designed to accommodate the 
effects of and be compatible with the environmental conditions 
associated with normal operation, maintenance, testing, and postulated 
accident conditions. Appendix B, ``Quality Assurance Criteria for 
Nuclear Power Plants and Fuel Reprocessing Plants,'' to 10 CFR Part 50 
requires that measures be established to ensure materials control and 
control of special processes such as welding and heat treating and to 
ensure performance of reliable testing programs. This guide describes 
acceptable methods of implementing the above requirements with regard 
to control of the application and processing of stainless steel to 
avoid severe sensitization that could lead to stress-corrosion 
cracking. This guide applies to light-water-cooled reactors.

II. Further Information

    The NRC staff is soliciting comments on DG-1224. Comments may be 
accompanied by relevant information or supporting data and should 
mention DG-1224 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-2009-0277]. Address 
questions about NRC dockets to Carol Gallagher, 301-492-3668; e-mail 
<a href="/cdn-cgi/l/email-protection#a3e0c2d1cccf8de4c2cfcfc2c4cbc6d1e3cdd1c08dc4ccd5"><span class="__cf_email__" data-cfemail="2b684a594447056c4a47474a4c434e596b455948054c445d">[email protected]</span></a>.
    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-1224 may be directed to 
the NRC contact, Jeffrey Hixon at (301) 251-7639 or e-mail to 
<a href="/cdn-cgi/l/email-protection#c68ca3a0a0b4a3bfe88eafbea9a886a8b4a5e8a1a9b0"><span class="__cf_email__" data-cfemail="b6fcd3d0d0c4d3cf98fedfced9d8f6d8c4d598d1d9c0">[email protected]</span></a>.
    Comments would be most helpful if received by August 31, 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-1224 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/doc-collections/. Electronic copies are also available in 
ADAMS (http://www.nrc.gov/reading-rm/adams.html), under Accession No. 
ML090750744.
    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 <a href="/cdn-cgi/l/email-protection#6c1c081e421e091f03191e0f092c021e0f420b031a"><span class="__cf_email__" data-cfemail="2b5b4f5905594e58445e59484e6b455948054c445d">[email protected]</span></a>.
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

    Dated at Rockville, Maryland, this 25th day of June 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. E9-15787 Filed 7-2-09; 8:45 am]
BILLING CODE 7590-01-P


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