Draft Regulatory Guide: Issuance, Availability, 49895-49896 [E9-23433]

Download as PDF Federal Register / Vol. 74, No. 187 / Tuesday, September 29, 2009 / Notices interested parties at the Permit Office, address below. ADDRESSES: Comments should be addressed to Permit Office, Room 755, Office of Polar Programs, National Science Foundation, 4201 Wilson Boulevard, Arlington, Virginia 22230. FOR FURTHER INFORMATION CONTACT: Nadene G. Kennedy at the above address or (703) 292–7405. SUPPLEMENTARY INFORMATION: The National Science Foundation, as directed by the Antarctic Conservation Act of 1978 (Pub. L. 95–541), as amended by the Antarctic Science, Tourism and Conservation Act of 1996, has developed regulations for the establishment of a permit system for various activities in Antarctica and designation of certain animals and certain geographic areas a requiring special protection. The regulations establish such a permit system to designate Antarctic Specially Protected Areas. The applications received are as follows: 1. Applicant: Permit Application No. 2010–016. Philip R. Kyle, Department of Earth & Environmental Science, New Mexico Institute of Mining and Technology, Socorro, NM 87801. Activity for Which Permit Is Requested Enter Antarctic Specially Protected Area. The applicant plans to enter Tramway Ridge, Mount Erebus (ASPA 130) measure soil temperatures and fluxes of CO2 and CO gases as part of the on-going surveillance of the active volcano. In addition, the applicant will undertake a survey of the geothermal features in the summit area of Mount Erebus. Location Tramway Ridge, Mount Erebus (ASPA 130). Dates December 1, 2009 to January 31, 2012. Nadene G. Kennedy, Permit Officer, Office of Polar Programs. [FR Doc. E9–23380 Filed 9–28–09; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION jlentini on DSKJ8SOYB1PROD with NOTICES [NRC–2009–0425] Draft Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, VerDate Nov<24>2008 16:18 Sep 28, 2009 Jkt 217001 DG–8039, ‘‘Methods for Estimating Effective Dose Equivalent from External Exposure.’’ FOR FURTHER INFORMATION CONTACT: Roger Pedersen, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001, telephone: (301) 415–3162, e-mail to Roger.Pedersen@nrc.gov. 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, ‘‘Methods for Estimating Effective Dose Equivalent from External Exposure,’’ is temporarily identified by its task number, DG–8039, which should be mentioned in all related correspondence. DG–8039 will be a new regulatory guide. This regulatory guide describes dosimetry methods that the NRC considers acceptable for determining effective dose equivalent for external (EDEX) radiation exposures. These methods provide a conservative estimate of EDEX and may be used to calculate TEDE in demonstrating compliance with TEDE-based regulatory requirements consistent with the provisions in 10 CFR 20.1201(c). Title 10, section 20.1003, ‘‘Definitions,’’ of the Code of Federal Regulations (10 CFR 20.1003) defines total effective dose equivalent (TEDE) as the sum of the effective dose equivalent (EDE) (for external exposures) and the committed EDE (for internal exposures). In 10 CFR 20.1201(a), the NRC provides an annual dose limit of 0.05 sievert (5 rem) TEDE and in 10 CFR 20.1201(c) requires that when an external personal monitoring device is used to measure external exposure, the deep-dose equivalent (DDE) must be used as an estimate of the EDE unless the EDE is determined more directly by a dosimetry method approved by the NRC. In using the DDE to estimate the EDE, the assigned DDE must be for the part of the body receiving the highest radiation exposure. PO 00000 Frm 00048 Fmt 4703 Sfmt 4703 49895 II. Further Information The NRC staff is soliciting comments on DG–8039. Comments may be accompanied by relevant information or supporting data and should mention DG–8039 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). Because your comments will not be edited to remove any identifying or contact information, the NRC cautions you against including any information in your submission that you do not want to be publicly disclosed. The NRC requests that any party soliciting or aggregating comments received from other persons for submission to the NRC inform those persons that the NRC will not edit their comments to remove any identifying or contact information, and therefore, they should not include any information in their comments that they do not want publicly disclosed. 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 https://www.regulations.gov and search for documents filed under Docket ID NRC–2009–0425. Address questions about NRC dockets to Carol Gallagher, 301–492–3668; e-mail Carol.Gallagher@nrc.gov. 3. Fax comments to: Rulemaking and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 492–3446. Comments would be most helpful if received by November 26, 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. Requests for technical information about DG–8039 may be directed to the NRC contact, Roger Pedersen at (301) 415–3162 or e-mail to Roger.Pedersen@nrc.gov. Electronic copies of DG–8039 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 E:\FR\FM\29SEN1.SGM 29SEN1 49896 Federal Register / Vol. 74, No. 187 / Tuesday, September 29, 2009 / Notices https://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also available in ADAMS (https:// www.nrc.gov/reading-rm/adams.html), under Accession No. ML091390066. 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 pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. Dated at Rockville, Maryland, this 3rd day of September 2009. For the Nuclear Regulatory Commission. Andrea D. Valentin, Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E9–23433 Filed 9–28–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2009–0427; Docket No. 030–10491] Notice of Availability of Environmental Assessment and Finding of No Significant Impact for License Amendment to Byproduct Materials License No. 29–16145–01, for Unrestricted Release of Robert Wood Johnson University Hospital at Hamilton’s Clinical Pharmacology Unit Located at #3 Hamilton Health Place, Hamilton, NJ AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact for license amendment. jlentini on DSKJ8SOYB1PROD with NOTICES FOR FURTHER INFORMATION CONTACT: ´ ´ Hector Bermudez, Sr. Health Physicist, Medical Branch, Division of Nuclear Materials Safety, Region I, 475 Allendale Road, King of Prussia, Pennsylvania 19406; telephone (404) 562–4734; fax number (610) 337–5269; or by e-mail: Hector.Bermudez@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is considering the issuance of a license amendment to byproduct materials License No. 29– 16145–01. This license is held by Robert Wood Johnson University Hospital at VerDate Nov<24>2008 16:18 Sep 28, 2009 Jkt 217001 Hamilton (the Licensee), for one of its facilities located at #3 Hamilton Health Place (the Facility). Issuance of the amendment would authorize release of the Facility for unrestricted use. The Licensee requested this action in a letter dated December 10, 2008. The NRC has prepared an Environmental Assessment (EA) in support of this proposed action in accordance with the requirements of Title 10, Code of Federal Regulations (CFR), Part 51 (10 CFR Part 51). Based on the EA, the NRC has concluded that a Finding of No Significant Impact (FONSI) is appropriate with respect to the proposed action. The amendment will be issued to the Licensee following the publication of this FONSI and EA in the Federal Register. II. Environmental Assessment Identification of Proposed Action The proposed action would approve the Licensee’s December 18, 2008, license amendment request, resulting in release of the Facility for unrestricted use. License No. 29–16145–01 was issued on September 19, 1974, to Hamilton Hospital (now Robert Wood Johnson University Hospital at Hamilton) pursuant to 10 CFR Part 30, and has been amended periodically since that time. This license authorizes the Licensee to use unsealed byproduct materials for the purposes of medical diagnosis and treatment of humans. The building that houses the Facility is a single story building located in a mixed residential/commercial area. The licensee occupied approximately 12,000 square feet of space in part of the building, consisting of office space and laboratories. Within the Facility, use of licensed materials was confined to Rooms 102, 103, 104, 126, 154, 180, 195C, 216, 217, 220, 221, and 242. Routine licensed activities ceased in 2008 and the licensee initiated a survey of the Facility. Based on the Licensee’s historical knowledge of the site and the conditions of the Facility, the Licensee determined that only routine decontamination activities, in accordance with the NRC-approved operating radiation safety procedures, would be required. The Licensee was not required to submit a decommissioning plan to the NRC because worker cleanup activities and procedures are consistent with those approved for routine operations. The Licensee conducted surveys of the Facility and provided information to the NRC to demonstrate that it meets the criteria in Subpart E of 10 CFR Part 20 for unrestricted release and for license termination. PO 00000 Frm 00049 Fmt 4703 Sfmt 4703 Need for the Proposed Action The Licensee has ceased conducting licensed activities at the Facility, and seeks the unrestricted use of its Facility. Environmental Impacts of the Proposed Action The historical review of licensed activities conducted at the Facility shows that such activities involved use of the following radionuclide with a half-life greater than 120 days in unsealed form: Carbon-14. The Licensee conducted a final status survey in April 2009. This survey covered all the areas of use at the Facility. The final status survey report was attached to the Licensee’s letter dated April 30, 2009. The Licensee elected to demonstrate compliance with the radiological criteria for unrestricted release as specified in 10 CFR 20.1402 by using the screening approach described in NUREG–1757, ‘‘Consolidated NMSS Decommissioning Guidance,’’ Volume 2. The Licensee used the radionuclidespecific derived concentration guideline levels (DCGLs), developed there by the NRC, which comply with the dose criterion in 10 CFR 20.1402. These DCGLs define the maximum amount of residual radioactivity on building surfaces, equipment, and materials, and in soils, that will satisfy the NRC requirements in Subpart E of 10 CFR Part 20 for unrestricted release. The Licensee’s final status survey results were below these DCGLs and are in compliance with the As Low As Reasonably Achievable (ALARA) requirement of 10 CFR 20.1402. The NRC thus finds that the Licensee’s final status survey results are acceptable. Based on its review the staff has determined that the affected environment and any environmental impacts associated with the proposed action are bounded by the impacts evaluated by the ‘‘Generic Environmental Impact Statement in Support of Rulemaking on Radiological Criteria for License Termination of NRC–Licensed Nuclear Facilities’’ (NUREG–1496) Volumes 1–3 (ML042310492, ML042320379, and ML042330385). The staff finds there were no significant environmental impacts from the use of radioactive material at the Facility. The NRC staff reviewed the docket file records and the final status survey report to identify any non-radiological hazards that may have impacted the environment surrounding the Facility. No such hazards or impacts to the environment were identified. The NRC has identified no other radiological or non-radiological activities in the area E:\FR\FM\29SEN1.SGM 29SEN1

Agencies

NUCLEAR REGULATORY COMMISSION

[Federal Register Volume 74, Number 187 (Tuesday, September 29, 2009)]
[Notices]
[Pages 49895-49896]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-23433]


=======================================================================
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NUCLEAR REGULATORY COMMISSION

[NRC-2009-0425]


Draft Regulatory Guide: Issuance, Availability

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, 
DG-8039, ``Methods for Estimating Effective Dose Equivalent from 
External Exposure.''

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

FOR FURTHER INFORMATION CONTACT: Roger Pedersen, U.S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 415-
3162, e-mail to Roger.Pedersen@nrc.gov.

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, ``Methods for Estimating 
Effective Dose Equivalent from External Exposure,'' is temporarily 
identified by its task number, DG-8039, which should be mentioned in 
all related correspondence. DG-8039 will be a new regulatory guide.
    This regulatory guide describes dosimetry methods that the NRC 
considers acceptable for determining effective dose equivalent for 
external (EDEX) radiation exposures. These methods provide a 
conservative estimate of EDEX and may be used to calculate TEDE in 
demonstrating compliance with TEDE-based regulatory requirements 
consistent with the provisions in 10 CFR 20.1201(c).
    Title 10, section 20.1003, ``Definitions,'' of the Code of Federal 
Regulations (10 CFR 20.1003) defines total effective dose equivalent 
(TEDE) as the sum of the effective dose equivalent (EDE) (for external 
exposures) and the committed EDE (for internal exposures). In 10 CFR 
20.1201(a), the NRC provides an annual dose limit of 0.05 sievert (5 
rem) TEDE and in 10 CFR 20.1201(c) requires that when an external 
personal monitoring device is used to measure external exposure, the 
deep-dose equivalent (DDE) must be used as an estimate of the EDE 
unless the EDE is determined more directly by a dosimetry method 
approved by the NRC. In using the DDE to estimate the EDE, the assigned 
DDE must be for the part of the body receiving the highest radiation 
exposure.

II. Further Information

    The NRC staff is soliciting comments on DG-8039. Comments may be 
accompanied by relevant information or supporting data and should 
mention DG-8039 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).
    Because your comments will not be edited to remove any identifying 
or contact information, the NRC cautions you against including any 
information in your submission that you do not want to be publicly 
disclosed.
    The NRC requests that any party soliciting or aggregating comments 
received from other persons for submission to the NRC inform those 
persons that the NRC will not edit their comments to remove any 
identifying or contact information, and therefore, they should not 
include any information in their comments that they do not want 
publicly disclosed. 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 https://www.regulations.gov 
and search for documents filed under Docket ID NRC-2009-0425. Address 
questions about NRC dockets to Carol Gallagher, 301-492-3668; e-mail 
Carol.Gallagher@nrc.gov.
    3. Fax comments to: Rulemaking and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission at (301) 492-3446.
    Comments would be most helpful if received by November 26, 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.
    Requests for technical information about DG-8039 may be directed to 
the NRC contact, Roger Pedersen at (301) 415-3162 or e-mail to 
Roger.Pedersen@nrc.gov.
    Electronic copies of DG-8039 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

[[Page 49896]]

https://www.nrc.gov/reading-rm/doc-collections/. Electronic copies are 
also available in ADAMS (https://www.nrc.gov/reading-rm/adams.html), 
under Accession No. ML091390066.
    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 pdr.resource@nrc.gov.
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

    Dated at Rockville, Maryland, this 3rd day of September 2009.

    For the Nuclear Regulatory Commission.
Andrea D. Valentin,
Chief, Regulatory Guide Development Branch, Division of Engineering, 
Office of Nuclear Regulatory Research.
[FR Doc. E9-23433 Filed 9-28-09; 8:45 am]
BILLING CODE 7590-01-P

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