Regulatory Guide 5.67, Material Control and Accounting for Uranium Enrichment Facilities Authorized To Produce Special Nuclear Material of Low Strategic Significance, 60482 [2012-24282]

Download as PDF 60482 Federal Register / Vol. 77, No. 192 / Wednesday, October 3, 2012 / Notices [FR Doc. 2012–24395 Filed 10–2–12; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2012–0227] Regulatory Guide 5.67, Material Control and Accounting for Uranium Enrichment Facilities Authorized To Produce Special Nuclear Material of Low Strategic Significance Nuclear Regulatory Commission. ACTION: Regulatory guide; withdrawal. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing Regulatory Guide (RG) 5.67, ‘‘Material Control and Accounting for Uranium Enrichment Facilities Authorized to Produce Special Nuclear Material of Low Strategic Significance.’’ The guide is being withdrawn because it is no longer needed and more extensive guidance can be found in NUREG/CR– 5734, ‘‘Recommendations to the NRC on Acceptable Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for LowEnriched Uranium Facilities’’ which was issued in November 1991. ADDRESSES: Please refer to Docket ID NRC–2012–0227 when contacting the NRC about the availability of information on this document. You may access information related to this document, which the NRC possesses and is publicly available, using the following methods: • Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC–2012–0227. Address questions about NRC dockets to Carol Gallagher; telephone: 301–492–3668; email: Carol.Gallagher@nrc.gov. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the NRC erowe on DSK2VPTVN1PROD with SUMMARY: VerDate Mar<15>2010 18:36 Oct 02, 2012 Jkt 229001 guidance in the withdrawn regulatory guide. Therefore, a certificate holder or licensee who wishes to follow the guidance bears the responsibility of demonstrating, in the appropriate circumstance, that the guidance in the withdrawn regulatory guide is applicable to the certificate holder or licensee’s specific situation. Current certificate holders or licensees who have included RG 5.67 in their licensing basis may continue to use it, and withdrawal of the guide does not affect their existing licensing documents or agreements. Changes to existing licenses (or 10 CFR part 76 certificates) must be accomplished in accordance with applicable NRC requirements. [FR Doc. 2012–24282 Filed 10–2–12; 8:45 am] I. Introduction Dated at Rockville, Maryland, this 26th day of Sept., 2012. For the Nuclear Regulatory Commission. Thomas H. Boyce, Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. Library at https://www.nrc.gov/readingrm/adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to pdr.resource@nrc.gov. The review of the withdrawal of RG 5.67 is available in ADAMS under Accession No. ML12110A280. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, Room O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Glenn Tuttle, Office of Nuclear Material Safety and Safeguards, Division of Fuel Cycle Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: 301–492–3129; or by email at Glenn.Tuttle@nrc.gov. SUPPLEMENTARY INFORMATION: defined in 10 CRF 50.109(a)(1) and is not otherwise inconsistent with the applicable issue finality provision in 10 CFR Part 52, inasmuch as such applicants or potential applicants are not within the scope of entities protected by the Backfit Rule or the relevant issue finality provisions in Part 52. BILLING CODE 7590–01–P The NRC is withdrawing RG 5.67 because its guidance is no longer needed. RG 5.67 was published in December 1993 to provide guidance to the Paducah and Portsmouth Gaseous Diffusion Plants (GDPs) to develop their material control and accounting (MC&A) programs under Title 10, Code of Federal Regulations (10 CFR) part 76. RG 5.67 was used in conjunction with the 10 CFR part 74 MC&A guidance in NUREG/CR–5734, ‘‘Recommendations to the NRC on Acceptable Format and Content for the Fundamental Nuclear Material Control (FNMC) Plan Required for Low-Enriched Uranium Facilities’’ to develop the FNMC plans for the two GDPs in the 1990s. The NRC is withdrawing this regulatory guide because NUREG/CR– 5734 is more comprehensive than RG 5.67 and is applicable to the Paducah GDP and other uranium enrichment facilities that have been licensed under 10 CFR part 70. Topics that are covered only briefly in RG 5.67 are covered in detail in NUREG/CR–5734. Therefore, the guidance in RG 5.67 is not needed. II. Further Information As discussed above, the guidance provided in RG 5.67 is no longer necessary and is addressed in more detail by NUREG/CR–5734. Regulatory guides may be withdrawn when their guidance no longer provides useful information. Withdrawal of a regulatory guide means that the NRC staff no longer approves, as a generic matter, the PO 00000 Frm 00110 Fmt 4703 Sfmt 4703 Dated at Rockville, Maryland, this 24th day of September, 2012. For the Nuclear Regulatory Commission. Thomas H. Boyce, Branch Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–029 and 72–31; NRC–2012– 0229] Yankee Atomic Electric Company; Yankee Rowe Independent Spent Fuel Storage Installation, Staff Evaluation; Exemption 1.0 Background Yankee Atomic Electric Company (YAEC, the licensee) is the holder of Facility Operating License No. DPR–3 which authorizes possession of nuclear fuel under part 50 of Title 10 of the Code of Federal Regulations (10 CFR). The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC or the Commission) now or hereafter in effect. Per 10 CFR part 72, Subpart K, a general license is issued for the storage of spent fuel in an Independent Spent Fuel Storage Installation (ISFSI) to persons authorized to possess or operate nuclear power reactors under 10 CFR part 50. Thus, YAEC also holds a 10 CFR part 72 general license for storage of spent fuel and greater than Class C waste at the Yankee Rowe ISFSI in Rowe, Massachusetts. The Yankee Nuclear Power Station (YNPS) was a Pressurized Water Reactor in Rowe, Massachusetts, operated by the Yankee Atomic Electric Company (YAEC). By February 26, 1992, the reactor core was removed, and YNPS E:\FR\FM\03OCN1.SGM 03OCN1

Agencies

[Federal Register Volume 77, Number 192 (Wednesday, October 3, 2012)]
[Notices]
[Page 60482]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2012-24282]


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NUCLEAR REGULATORY COMMISSION

[NRC-2012-0227]


Regulatory Guide 5.67, Material Control and Accounting for 
Uranium Enrichment Facilities Authorized To Produce Special Nuclear 
Material of Low Strategic Significance

AGENCY: Nuclear Regulatory Commission.

ACTION: Regulatory guide; withdrawal.

-----------------------------------------------------------------------

SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) is withdrawing 
Regulatory Guide (RG) 5.67, ``Material Control and Accounting for 
Uranium Enrichment Facilities Authorized to Produce Special Nuclear 
Material of Low Strategic Significance.'' The guide is being withdrawn 
because it is no longer needed and more extensive guidance can be found 
in NUREG/CR-5734, ``Recommendations to the NRC on Acceptable Format and 
Content for the Fundamental Nuclear Material Control (FNMC) Plan 
Required for Low-Enriched Uranium Facilities'' which was issued in 
November 1991.

ADDRESSES: Please refer to Docket ID NRC-2012-0227 when contacting the 
NRC about the availability of information on this document. You may 
access information related to this document, which the NRC possesses 
and is publicly available, using the following methods:
     Federal Rulemaking Web site: Go to https://www.regulations.gov and search for Docket ID NRC-2012-0227. Address 
questions about NRC dockets to Carol Gallagher; telephone: 301-492-
3668; email: Carol.Gallagher@nrc.gov.
     NRC's Agencywide Documents Access and Management System 
(ADAMS): You may access publicly available documents online in the NRC 
Library at https://www.nrc.gov/reading-rm/adams.html. To begin the 
search, select ``ADAMS Public Documents'' and then select ``Begin Web-
based ADAMS Search.'' For problems with ADAMS, please contact the NRC's 
Public Document Room (PDR) reference staff at 1-800-397-4209, 301-415-
4737, or by email to pdr.resource@nrc.gov. The review of the withdrawal 
of RG 5.67 is available in ADAMS under Accession No. ML12110A280.
     NRC's PDR: You may examine and purchase copies of public 
documents at the NRC's PDR, Room O1-F21, One White Flint North, 11555 
Rockville Pike, Rockville, Maryland 20852.

FOR FURTHER INFORMATION CONTACT: Glenn Tuttle, Office of Nuclear 
Material Safety and Safeguards, Division of Fuel Cycle Safety and 
Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555-
0001, telephone: 301-492-3129; or by email at Glenn.Tuttle@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The NRC is withdrawing RG 5.67 because its guidance is no longer 
needed. RG 5.67 was published in December 1993 to provide guidance to 
the Paducah and Portsmouth Gaseous Diffusion Plants (GDPs) to develop 
their material control and accounting (MC&A) programs under Title 10, 
Code of Federal Regulations (10 CFR) part 76. RG 5.67 was used in 
conjunction with the 10 CFR part 74 MC&A guidance in NUREG/CR-5734, 
``Recommendations to the NRC on Acceptable Format and Content for the 
Fundamental Nuclear Material Control (FNMC) Plan Required for Low-
Enriched Uranium Facilities'' to develop the FNMC plans for the two 
GDPs in the 1990s.
    The NRC is withdrawing this regulatory guide because NUREG/CR-5734 
is more comprehensive than RG 5.67 and is applicable to the Paducah GDP 
and other uranium enrichment facilities that have been licensed under 
10 CFR part 70. Topics that are covered only briefly in RG 5.67 are 
covered in detail in NUREG/CR-5734. Therefore, the guidance in RG 5.67 
is not needed.

II. Further Information

    As discussed above, the guidance provided in RG 5.67 is no longer 
necessary and is addressed in more detail by NUREG/CR-5734. Regulatory 
guides may be withdrawn when their guidance no longer provides useful 
information.
    Withdrawal of a regulatory guide means that the NRC staff no longer 
approves, as a generic matter, the guidance in the withdrawn regulatory 
guide. Therefore, a certificate holder or licensee who wishes to follow 
the guidance bears the responsibility of demonstrating, in the 
appropriate circumstance, that the guidance in the withdrawn regulatory 
guide is applicable to the certificate holder or licensee's specific 
situation. Current certificate holders or licensees who have included 
RG 5.67 in their licensing basis may continue to use it, and withdrawal 
of the guide does not affect their existing licensing documents or 
agreements. Changes to existing licenses (or 10 CFR part 76 
certificates) must be accomplished in accordance with applicable NRC 
requirements.

    Dated at Rockville, Maryland, this 24th day of September, 2012.

    For the Nuclear Regulatory Commission.
Thomas H. Boyce,
Branch Chief, Regulatory Guide Development Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. 2012-24282 Filed 10-2-12; 8:45 am]
BILLING CODE 7590-01-P
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