Notice of Issuance of Regulatory Guide, 55544-55545 [E8-22534]

Download as PDF 55544 Federal Register / Vol. 73, No. 187 / Thursday, September 25, 2008 / Notices Management and Budget, Washington, DC 20503. Comments can also be e-mailed to Nathan_J._Frey@omb.eop.gov or submitted by telephone at (202) 395– 7345. The NRC Clearance Officer is Russell Nichols, (301) 415–6874. Dated at Rockville, Maryland, this 18th day of September, 2008. For the Nuclear Regulatory Commission. Gregory Trussell, Acting NRC Clearance Officer, Office of Information Services. [FR Doc. E8–22531 Filed 9–24–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Notice of Issuance of Regulatory Guide Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 10.7, Revision 2. AGENCY: II. Further Information FOR FURTHER INFORMATION CONTACT: mstockstill on PROD1PC66 with NOTICES Mark Orr, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone (301) 415– 6373 or e-mail to Mark.Orr@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to an existing 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. Revision 2 of Regulatory Guide 10.7, ‘‘Guide for the Preparation of Applications for Licenses for Laboratory and Industrial Use of Small Quantities of Byproduct Material,’’ was issued with a temporary identification as Draft Regulatory Guide, DG–0017. This guide directs the reader to the type of information needed by the NRC staff to evaluate an application for a specific license for laboratories and industries to use megabecquerel (MBq) (millicurie (mCi)) quantities of byproduct material (reactor- or accelerator-produced radionuclides). VerDate Aug<31>2005 17:50 Sep 24, 2008 Jkt 214001 The regulatory framework that the NRC has established for laboratory and industrial use of small quantities of byproduct material is in Title 10, Part 30, ‘‘Rules of General Applicability to Domestic Licensing of Byproduct Material,’’ of the Code of Federal Regulations (10 CFR part 30). This regulatory guide endorses the methods and procedures for applying for a license for laboratory and industrial use of small quantities of byproduct material contained in the current revisions of NUREG–1556, Volume 7, ‘‘Consolidated Guidance About Materials Licenses: ProgramSpecific Guidance About Academic, Research and Development, and Other Licenses of Limited Scope’’ and NUREG–1556, Volume 12, ‘‘Consolidated Guidance about Material Licenses: Program-Specific Guidance About Possession and Licenses for Manufacturing and Distribution,’’ as a process that the NRC staff finds acceptable. In April 2008, DG–0017 was published with a public comment period of 60 days from the issuance of the guide. No comments were received and the public comment period closed on June 30, 2008. Electronic copies of Regulatory Guide 10.7, Revision 2 are available through the NRC’s public Web site under ‘‘Regulatory Guides’’ at http://www.nrc.gov/reading-rm/doccollections/. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR), which is located at Room O–1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852–2738. 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) 397–4209, by fax at (301) 415–3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. Dated at Rockville, Maryland, this 18th day of September, 2008. For the Nuclear Regulatory Commission. Stephen C. O’Connor, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E8–22532 Filed 9–24–08; 8:45 am] BILLING CODE 7590–01–P PO 00000 Frm 00049 Fmt 4703 Sfmt 4703 NUCLEAR REGULATORY COMMISSION Notice of Issuance of Regulatory Guide Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Regulatory Guide 10.9, Revision 2. AGENCY: FOR FURTHER INFORMATION CONTACT: Mark Orr, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone (301) 415– 6373 or e-mail to Mark.Orr@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision to an existing 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. Revision 2 of Regulatory Guide 10.9, ‘‘Guide for the Preparation of Applications for the Use of SelfContained Dry Source-Storage Gamma Irradiators,’’ was issued with a temporary identification as Draft Regulatory Guide, DG–0019. This regulatory guide directs the reader to the type of information acceptable to the NRC staff for review of an application for the use of a self-contained dry source-storage gamma irradiator. Title 10, Part 36, ‘‘Licenses and Radiation Safety Requirements for Irradiators,’’ of the Code of Federal Regulations (10 CFR Part 36) contains the licensing, design, and radiation safety requirements for irradiators. In addition, licensees and applicants may be subject to portions of the requirements in 10 CFR Part 30, ‘‘Rules of General Applicability to Domestic Licensing of Byproduct Material,’’ and 10 CFR Part 20, ‘‘Standards for Protection Against Radiation.’’ This regulatory guide endorses the methods and procedures describing how to apply for a license to use a selfcontained dry source-storage gamma irradiator contained in the current revision of NUREG 1556, Volume 5, ‘‘Consolidated Guidance about Material Licenses: Program-Specific Guidance E:\FR\FM\25SEN1.SGM 25SEN1 Federal Register / Vol. 73, No. 187 / Thursday, September 25, 2008 / Notices and the termination of the TR–02 license is administrative in nature. about Self-Shielded Irradiator Licenses,’’ as a process that the NRC staff finds acceptable for meeting the regulatory requirements. II. Further Information In April 2008, DG–0019 was published with a public comment period of 60 days from the issuance of the guide. No comments were received and the public comment period closed on June 30, 2008. Electronic copies of Regulatory Guide 10.9, Revision 2 are available through the NRC’s public Web site under ‘‘Regulatory Guides’’ at http://www.nrc.gov/reading-rm/doccollections/. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR), which is located at Room O–1F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852–2738. 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) 397–4209, by fax at (301) 415–3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and NRC approval is not required to reproduce them. Dated at Rockville, Maryland, this 18th day of September 2008. For the Nuclear Regulatory Commission. Stephen C. O’Connor, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E8–22534 Filed 9–24–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–022] mstockstill on PROD1PC66 with NOTICES Notice of License Termination CBS Test Reactor Located at Waltz Mill Site, Madison, PA Introduction The U.S. Nuclear Regulatory Commission (NRC) is noticing the granting of an exemption from 10 CFR 50.82(b)(6)(ii), and the related termination of Facility Operating License No. TR–02, held by CBS for the test reactor (TR) located on the Waltz Mill Site in Madison, PA. CBS requested this action in a letter to NRC dated December 6, 2007 (ML073440024). As discussed below, Westinghouse Electric Company, LLC (Westinghouse) held NRC materials license SNM–770, a license covering the entire Waltz Mill site on which the former TR was located. The granting of this exemption VerDate Aug<31>2005 17:50 Sep 24, 2008 Jkt 214001 Background The initial license for the TR was issued on June 19, 1959. Reactor operation permanently ceased following an accident in 1960. On March 25, 1963, the license was amended to allow only possession of special nuclear material but not reactor operation. A Decommissioning Plan (DP) for the TR was submitted on July 27, 1997, and was approved on September 30, 1998. In the context of facilitating the resolution of a then-pending arbitration dispute regarding the Waltz Mill site between CBS and Westinghouse, the NRC, by letter dated March 17, 2006 (ML060750730), advised the parties that a request for an exemption from 10 CFR 50.82(b)(6)(ii) should be submitted jointly by CBS and Westinghouse, or by CBS with concurrence or an affidavit from Westinghouse, stating Westinghouse’s willingness to accept the TR facility in the condition it was left in by CBS. This guidance further stated that the NRC would terminate the TR–2 license when: (1) The SNM–770 license was amended to accept the transfer of all residual radioactive materials, equipment and structures associated with the TR–2 license; and, (2) the NRC’s requirements for terminating non-power reactor licenses had been satisfied. The arbitration case between CBS and Westinghouse resulted in a final arbitration opinion and award (American Arbitration Association Case No. 16Y 192 00937 02 dated July 20, 2007). In August 2007, CBS reached a monetary settlement with Westinghouse regarding the completion of decommissioning activities at TR–2. In a letter dated December 6, 2007, Westinghouse requested that its SNM– 770 license be amended to accept the TR–2 radioactive materials, structures, and equipment (ML073620136). In this letter, Westinghouse acknowledged that it will have the sole responsibility for satisfying the NRC’s decommissioning requirements applicable to the Waltz Mill site, including requirements applicable to the radioactive materials, structures, and equipment associated with the former TR. On March 20, 2008, NRC conducted an inspection of the Waltz Mill site for the purpose of assessing the transfer of all residual radioactive material, equipment, and structures from the TR– 2 license to Westinghouse’s SNM–770 license. No violations were identified during the course of the inspection. On March 26, 2008, the requested amendment was issued authorizing Westinghouse under its license to take PO 00000 Frm 00050 Fmt 4703 Sfmt 4703 55545 possession of all remaining radioactive material, structures and equipment associated with the TR–2 facility. With this amendment to the SNM–770 license, the need for the separate TR–2 license ended. With the termination of the TR–2 license, the SNM–770 license was the only NRC license in effect for radioactive materials on the Waltz Mill Site. On March 31, 2008, the State of Pennsylvania became an NRC Agreement State. Subsequently, the SNM–770 license was re-issued by Pennsylvania as license PA 1053S. Discussion A. Requirements for Terminating NonPower Reactor Licenses The NRC’s regulations in 10 CFR 50.82(b)(6) provide that the Commission will terminate a non-power reactor license if it determines that the decommissioning has been performed in accordance with the approved decommissioning plan, and the terminal radiation survey and associated documentation demonstrate that the facility and site are suitable for release in accordance with Subpart E of 10 CFR part 20. (1) Compliance with the Decommissioning Plan (10 CFR 50.82(b)(6)(i)) As stated above, the NRC approved the TR–2 DP in 1998. DP Revision 1 (the only revision) revised the method for removing the pressure vessel from the TR–2 containment building. The reactor component and equipment removal actions required by the TR–2 DP have been successfully completed. In its March 2006 guidance letter, the NRC advised CBS that the only actions then needed to complete implementation of the TR–2 DP were: (1) Provide documentation showing that the remaining radioactive materials associated with the TR–2 facility would be transferred to the SNM–770 License; and (2) issuance of a license amendment to the SNM–770 License authorizing the transfer of this material. Those actions have now been taken and implementation of the TR–2 DP is thus complete. Accordingly, the NRC finds that the requirements of 10 CFR 50.82(b)(6)(i) have been met. (2) Terminal Radiation Survey and Associated Documentation (10 CFR 50.82(b)(6)(ii)) In addition to showing that decommissioning has been performed in accordance with the approved DP, a radiation survey and associated documentation must show that the facility and site are suitable for release in accordance with Subpart E of 10 CFR Part 20 before a non-power reactor license may be terminated. This is the E:\FR\FM\25SEN1.SGM 25SEN1

Agencies

[Federal Register Volume 73, Number 187 (Thursday, September 25, 2008)]
[Notices]
[Pages 55544-55545]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-22534]


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NUCLEAR REGULATORY COMMISSION


Notice of Issuance of Regulatory Guide

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Issuance and Availability of Regulatory Guide 10.9, 
Revision 2.

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FOR FURTHER INFORMATION CONTACT: Mark Orr, Regulatory Guide Development 
Branch, Division of Engineering, Office of Nuclear Regulatory Research, 
U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, 
telephone (301) 415-6373 or e-mail to Mark.Orr@nrc.gov.

SUPPLEMENTARY INFORMATION:

I. Introduction

    The U.S. Nuclear Regulatory Commission (NRC) is issuing a revision 
to an existing 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.
    Revision 2 of Regulatory Guide 10.9, ``Guide for the Preparation of 
Applications for the Use of Self-Contained Dry Source-Storage Gamma 
Irradiators,'' was issued with a temporary identification as Draft 
Regulatory Guide, DG-0019. This regulatory guide directs the reader to 
the type of information acceptable to the NRC staff for review of an 
application for the use of a self-contained dry source-storage gamma 
irradiator. Title 10, Part 36, ``Licenses and Radiation Safety 
Requirements for Irradiators,'' of the Code of Federal Regulations (10 
CFR Part 36) contains the licensing, design, and radiation safety 
requirements for irradiators. In addition, licensees and applicants may 
be subject to portions of the requirements in 10 CFR Part 30, ``Rules 
of General Applicability to Domestic Licensing of Byproduct Material,'' 
and 10 CFR Part 20, ``Standards for Protection Against Radiation.''
    This regulatory guide endorses the methods and procedures 
describing how to apply for a license to use a self-contained dry 
source-storage gamma irradiator contained in the current revision of 
NUREG 1556, Volume 5, ``Consolidated Guidance about Material Licenses: 
Program-Specific Guidance

[[Page 55545]]

about Self-Shielded Irradiator Licenses,'' as a process that the NRC 
staff finds acceptable for meeting the regulatory requirements.

II. Further Information

    In April 2008, DG-0019 was published with a public comment period 
of 60 days from the issuance of the guide. No comments were received 
and the public comment period closed on June 30, 2008. Electronic 
copies of Regulatory Guide 10.9, Revision 2 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), which is located at Room O-1F21, One 
White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852-
2738. 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) 397-4209, by fax at (301) 415-3548, and by e-mail to 
pdr.resource@nrc.gov.
    Regulatory guides are not copyrighted, and NRC approval is not 
required to reproduce them.

    Dated at Rockville, Maryland, this 18th day of September 2008.

    For the Nuclear Regulatory Commission.
Stephen C. O'Connor,
Acting Chief, Regulatory Guide Development Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. E8-22534 Filed 9-24-08; 8:45 am]
BILLING CODE 7590-01-P