Federal Register / Vol. 74, No. 187 / Tuesday, September 29, 2009 / Notices 49895 

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 

[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 

http://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 


jlentini on DSKJ8SOYB1PROD with NOTICES
49896 Federal Register / Vol. 74, No. 187 / Tuesday, September 29, 2009 / Notices 

http://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also 

available in ADAMS (http:// 

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. 

FOR FURTHER INFORMATION CONTACT: 

He ́ctor Bermu ́dez, 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 

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. 

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 


jlentini on DSKJ8SOYB1PROD with NOTICES