Withdrawal of Regulatory Guide, 7766 [E8-2423]

Download as PDF 7766 Federal Register / Vol. 73, No. 28 / Monday, February 11, 2008 / Notices NRC IMPORT LICENSE APPLICATION [Description of material] Name of applicant, date of application, date received, application No., docket No. EnergySolutions, September 14, 2007 (ML072950080), September 17, 2007 IW023, 11005711. Additional Information: December 5, 2007 (ML073400154), January 11, 2008 (ML080150374). Material type Total quantity End use Up to approximately 20,000 tons of radioactively contaminated material from nuclear facility operations; consisting of contaminated metals, graphite, dry activity material (e.g., wood, paper, and plastic), liquids (e.g., aqueous and organic-based fluids), and ion exchange resins (treated and untreated). Total volume estimated to be approximately 1,000,000 cubic feet. Quantities, types and combinations of radioactive contaminants will vary depending on material, but at no time will they exceed importer’s possession limits. The cumulative total quantity for each type of contaminant over the duration of the import license will not exceed 5 kilograms (kg) special nuclear material; 1.0 x 106 kg natural/depleted uranium; 20 TBq transuranics (except Pu); and 600 TBq of all other radionuclides. Contaminated materials are to be inspected, sorted and processed at applicant’s facilities in and licensed by the State of Tennessee for recycle and beneficial reuse and/or disposal of as radioactive waste (pending conformity with waste acceptance criteria) at a Clive, Utah disposal facility licensed by the State of Utah. Materials that meet domestic license conditions for unrestricted release may be released. Nonconforming materials would be returned to the generator (see associated export license application XW013). Dated this 5th day of February 2008 at Rockville, Maryland. For the Nuclear Regulatory Commission. Scott W. Moore, Deputy Director, Office of International Programs. [FR Doc. E8–2484 Filed 2–8–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Withdrawal of Regulatory Guide Nuclear Regulatory Commission. ACTION: Notice of Withdrawal of Regulatory Guide 1.176. AGENCY: FOR FURTHER INFORMATION CONTACT: rwilkins on PROD1PC63 with NOTICES Christina Antonescu, Reactor System Engineer, Division of Engineering, Regulatory Guide Development Branch, Office of Nuclear Reactor Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: 301–415–6792 or e-mail: CEA1@NRC.GOV. SUPPLEMENTARY INFORMATION: I. Introduction The Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 1.176, ‘‘An Approach for PlantSpecific, Risk-Informed Decisionmaking: Graded Quality Assurance,’’ which was published in August 1998, but has been superseded by subsequent rulemaking. In November 2004, the NRC promulgated Title 10 of the Code of VerDate Aug<31>2005 16:44 Feb 08, 2008 Jkt 214001 Country of origin Italy. Federal Regulations (10 CFR) section 50.69, ‘‘Risk-informed categorization and treatment of structures, systems, and components for nuclear power reactors,’’ (69 FR 68008) to permit power reactor licensees and license applicants to implement an alternative regulatory framework with respect to ‘‘special treatment,’’ where special treatment refers to those requirements that provides increased quality assurance beyond normal industrial practices that structures, systems, and components (SSCs) perform their design-basis functions. In support of 10 CFR 50.69, the staff issued RG 1.201, ‘‘Guidelines for Categorizing Structures, Systems and Components in Nuclear Power Plants According to Their Safety Significance,’’ in January 2006 for trial use. This new framework, consisting of the rule along with RG 1.201, has made the guidance in RG 1.176 obsolete. Reading Room at https://www.nrc.gov/ reading-rm/doc-collections. RGs are also available for inspection at the NRC’s Public Document Room (PDR), Room O–1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852–2738. The PDR’s mailing address is U.S. NRC PDR, Washington, DC 20555–0001. The PDR staff can be reached by telephone at 301–415–4737 or 800–397–4209, by fax at 301–415– 3548, and by e-mail to pdr@nrc.gov. RGs are not copyrighted and NRC approval is not required to reproduce them. II. Further Information BILLING CODE 7590–01–P The withdrawal of RG 1.176 does not, in and of itself, alter any prior or existing licensing commitments based on its use. The current version of RG 1.176 represents a method that is no longer acceptable to the staff. RGs may be withdrawn when their guidance is superseded by congressional action, the methods or techniques described in the RG no longer describe an acceptable approach, or the RG does not provide useful information. RGs are available for inspection or downloading through the NRC’s public Web site under ‘‘Regulatory Guides’’ collection in the NRC’s Electronic PO 00000 Frm 00072 Fmt 4703 Sfmt 4703 Dated at Rockville, Maryland, this 4th day of February, 2008. For the Nuclear Regulatory Commission. Andrea D. Valentin, Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E8–2423 Filed 2–8–08; 8:45 am] NUCLEAR REGULATORY COMMISSION Withdrawal of Regulatory Guide Nuclear Regulatory Commission. ACTION: Notice of withdrawal of Regulatory Guide 1.150. AGENCY: FOR FURTHER INFORMATION CONTACT: Christina Antonescu, Reactor System Engineer, Division of Engineering, Regulatory Guide Development Branch, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, E:\FR\FM\11FEN1.SGM 11FEN1

Agencies

[Federal Register Volume 73, Number 28 (Monday, February 11, 2008)]
[Notices]
[Page 7766]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-2423]


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NUCLEAR REGULATORY COMMISSION


Withdrawal of Regulatory Guide

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Withdrawal of Regulatory Guide 1.176.

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FOR FURTHER INFORMATION CONTACT: Christina Antonescu, Reactor System 
Engineer, Division of Engineering, Regulatory Guide Development Branch, 
Office of Nuclear Reactor Research, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001, telephone: 301-415-6792 or e-mail: 
CEA1@NRC.GOV.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The Nuclear Regulatory Commission (NRC) is withdrawing Regulatory 
Guide (RG) 1.176, ``An Approach for Plant-Specific, Risk-Informed 
Decisionmaking: Graded Quality Assurance,'' which was published in 
August 1998, but has been superseded by subsequent rulemaking.
    In November 2004, the NRC promulgated Title 10 of the Code of 
Federal Regulations (10 CFR) section 50.69, ``Risk-informed 
categorization and treatment of structures, systems, and components for 
nuclear power reactors,'' (69 FR 68008) to permit power reactor 
licensees and license applicants to implement an alternative regulatory 
framework with respect to ``special treatment,'' where special 
treatment refers to those requirements that provides increased quality 
assurance beyond normal industrial practices that structures, systems, 
and components (SSCs) perform their design-basis functions. In support 
of 10 CFR 50.69, the staff issued RG 1.201, ``Guidelines for 
Categorizing Structures, Systems and Components in Nuclear Power Plants 
According to Their Safety Significance,'' in January 2006 for trial 
use. This new framework, consisting of the rule along with RG 1.201, 
has made the guidance in RG 1.176 obsolete.

II. Further Information

    The withdrawal of RG 1.176 does not, in and of itself, alter any 
prior or existing licensing commitments based on its use. The current 
version of RG 1.176 represents a method that is no longer acceptable to 
the staff. RGs may be withdrawn when their guidance is superseded by 
congressional action, the methods or techniques described in the RG no 
longer describe an acceptable approach, or the RG does not provide 
useful information.
    RGs are available for inspection or downloading through the NRC's 
public Web site under ``Regulatory Guides'' collection in the NRC's 
Electronic Reading Room at https://www.nrc.gov/reading-rm/doc-
collections. RGs are also available for inspection at the NRC's Public 
Document Room (PDR), Room O-1F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852-2738. The PDR's mailing 
address is U.S. NRC PDR, Washington, DC 20555-0001. The PDR staff can 
be reached by telephone at 301-415-4737 or 800-397-4209, by fax at 301-
415-3548, and by e-mail to pdr@nrc.gov.
    RGs are not copyrighted and NRC approval is not required to 
reproduce them.

    Dated at Rockville, Maryland, this 4th day of February, 2008.

    For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch, Division of Engineering, 
Office of Nuclear Regulatory Research.
[FR Doc. E8-2423 Filed 2-8-08; 8:45 am]
BILLING CODE 7590-01-P
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