Federal Register / Vol. 72, No. 95 / Thursday, May 17, 2007 / Notices 27857 

It is imperative that the meeting be 

held on these dates to accommodate the 

scheduling priorities of the key 

participants. Attendees will be 

requested to sign a register and to 

comply with NASA security 

requirements, including the 

presentation of a valid picture ID, before 

receiving an access badge. Foreign 

nationals attending this meeting will be 

required to provide the following 

information no less than 5 working days 

prior to the meeting: Full name; gender; 

date/place of birth; citizenship; visa/ 

green card information (number, type, 

expiration date); passport information 

(number, country, expiration date); 

employer/affiliation information (name 

of institution, address, country, 

telephone); title/position of attendee. To 

expedite admittance, attendees with 

U.S. citizenship can provide identifying 

information 5 working days in advance 

by contacting Marian Norris via e-mail 

at mnorris@nasa.gov or by telephone at 

(202) 358–4452. 

Dated: May 10, 2007. 

P. Diane Rausch, 

Advisory Committee Management Officer, 

National Aeronautics and Space 

Administration. 

[FR Doc. E7–9448 Filed 5–16–07; 8:45 am] 

BILLING CODE 7510–13–P 

NUCLEAR REGULATORY 

COMMISSION 

[ Docket No. 50–271–LR; ASLBP No. 06–

849–03–LR] 

Atomic Safety and Licensing Board; In 

the Matter of Entergy Nuclear Vermont 

Yankee, L.L.C., and Entergy Nuclear 

Operations, Inc. (Vermont Yankee 

Nuclear Power Station); Notice of 

Hearing (Application for License 

Renewal) 

May 11, 2007. 

Before Administrative Judges: Alex S. 

Karlin, Chairman, Dr. Richard E. 

Wardwell, Dr. Thomas S. Elleman. 

This proceeding concerns the January 

25, 2006, application of Entergy Nuclear 

Vermont Yankee, L.L.C., and Entergy 

Nuclear Operations, Inc. (collectively, 

Entergy), to renew the operating license 

for the Vermont Yankee Nuclear Power 

Station in Windham County, Vermont 

(Operating License No. DPR–28). 

Entergy seeks to extend this license for 

an additional twenty years beyond the 

current expiration date of March 21, 

2012. On March 27, 2006, the 

Commission published a notice of 

acceptance for docketing of the Entergy 

renewal application and a notice of 

opportunity to request a hearing on the 

application. 71 FR 15,220 (Mar. 27, 

2006). Requests for hearings and 

petitions to intervene were filed on or 

before May 26, 2006, by four entities: 

The Vermont Department of Public 

Service (DPS), the Attorney General of 

the Commonwealth of Massachusetts, 

the Town of Marlboro, Vermont, and the 

New England Coalition (NEC). On June 

14, 2006, this Atomic Safety and 

Licensing Board was established to 

conduct this adjudication. 71 FR 34,397 

(June 14, 2006). 

On August 1 and 2, 2006, the Board 

heard oral argument from the 

petitioners, Entergy, and the NRC Staff 

in Brattleboro, Vermont, relating to the 

admissibility of the proposed 

contentions. The standing of the 

petitioners to intervene was 

uncontested. On September 22, 2006, 

the Board issued a Memorandum and 

Order admitting contentions submitted 

by DPS and NEC, thereby granting two 

of the requests for a hearing and 

admitting DPS and NEC as parties to the 

proceeding. LBP–06–20, 64 NRC 131, 

143 (2006). At the same time, the Board 

also granted these two organizations’

requests to adopt one another’s 

contentions under 10 CFR 2.309(f)(3). 

On November 17, 2006, the Board 

granted the request by the State of New 

Hampshire to participate in this 

proceeding as an interested state under 

10 CFR 2.315(c). 

In light of the foregoing, please take 

notice that an evidentiary hearing will 

be conducted in this proceeding. 

Subject to a Board determination 

regarding any request to employ formal 

hearing procedures under 10 CFR part 2, 

subpart G or expedited hearing 

procedures under 10 CFR part 2, subpart 

N, see 10 CFR 2.310, the evidentiary 

hearing on all admitted contentions will 

be governed by the informal hearing 

procedures set forth in 10 CFR part 2, 

subpart L, 10 CFR 2.1200—2.1213. 

During the course of the proceeding, the 

Board may also hear oral arguments as 

provided in 10 CFR 2.331, may hold 

various prehearing conferences 

pursuant to 10 CFR 2.329, and may 

conduct evidentiary hearings in 

accordance with 10 CFR 2.1206–2.1208. 

These may be held via teleconference, 

video-conference, and/or in person. The 

public may attend any oral argument, 

prehearing conference, or evidentiary 

hearing. Notices of these sessions will 

be published in the Federal Register 

and/or made available to the public at 

the NRC Public Document Room (PDR), 

located at One White Flint North, 11555 

Rockville Pike (first floor), Rockville, 

Maryland, and through the NRC Web 

site, http://www.nrc.gov. 

Additionally, as provided in 10 CFR 

2.315(a), any ‘‘person who is not a 

party’’ to the proceeding may submit a 

written limited appearance statement. 

Limited appearance statements do not 

constitute evidence, but they are placed 

in the docket for the hearing and 

provide members of the public with an 

opportunity to make the Board and/or 

the parties aware of their concerns about 

matters at issue in the proceeding. A 

written limited appearance statement 

can be submitted at any time and should 

be sent to the Office of the Secretary 

using one of the following methods: (1) 

Mail to the Office of the Secretary, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001, Attention: 

Rulemakings and Adjudications Staff, 

with a copy to the Chairman of this 

Licensing Board at Mail Stop T–3F23, 

Atomic Safety and Licensing Board 

Panel, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555–

0001; (2) e-mail to the Office of the 

Secretary at hearingdocket@nrc.gov, 

with a copy to the Board Chairman 

(c/o Marcia Carpentier, mxc7@nrc.gov); 

or (3) fax to the Office of the Secretary 

at 301–415–1101 (facsimile verification 

number: 301–415–1966), with a copy to 

the Board Chairman at 301–415–5599 

(facsimile verification number: 301–

415–7550). 

At a later date, the Board may, at its 

discretion, hear oral limited appearance 

statements at a location in the vicinity 

of the Vermont Yankee facility. Notice 

of any oral limited appearance sessions 

will be published in the Federal 

Register and/or made available to the 

public at the NRC PDR and on the NRC 

Web site, http://www.nrc.gov. 

The deadline for this Board’s receipt 

of limited appearance statements 

(written or oral) will be the day 

preceding the commencement of the 

evidentiary hearing. The evidentiary 

hearing will occur after the NRC Staff 

issues its final environmental report and 

final safety evaluation report on this 

application. Thus, the evidentiary 

hearing has not yet been specifically 

scheduled, but will probably commence 

in early 2008. 

Documents relating to this proceeding 

are available for public inspection at the 

Commission’s PDR or electronically 

from the publicly available records 

component of NRC’s document system 

(ADAMS). ADAMS is accessible from 

the NRC Web site at http://www.nrc.gov/ 

reading-rm/adams.html (the Public 

Electronic Reading Room). Persons who 

do not have access to ADAMS, or who 

encounter problems in accessing the 

documents located in ADAMS, should 

contact the NRC PDR Reference staff by 


pwalker on PROD1PC71 with NOTICES
27858 Federal Register / Vol. 72, No. 95 / Thursday, May 17, 2007 / Notices 

1Copies of this order were sent this date by 

Internet e-mail transmission to counsel for (1) 

licensees Entergy Nuclear Vermont Yankee, L.L.C., 

and Entergy Nuclear Operations, Inc.; (2) 

intervenors Vermont Department of Public Service 

and New England Coalition of Brattleboro, 

Vermont; (3) the Staff and (4) the State of New 

Hampshire. 

telephone at 1–800–397–4209 or 301–

415–4737, or by e-mail at pdr@nrc.gov. 

It is so ordered. 

Dated: May 11, 2007. 

For the Atomic Safety and Licensing 

Board.1

Alex S. Karlin, 

Chairman, Administrative Judge, Rockville, 

Maryland. 

[FR Doc. E7–9524 Filed 5–16–07; 8:45 am] 

BILLING CODE 7590–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 030–19324] 

Notice of Availability of Environmental 

Assessment and Finding of No 

Significant Impact for License 

Amendment to Byproduct Materials 

License No. 25–19852–01 For 

Unrestricted Release Of Building 7 of 

the Glaxosmithkline BiologicalsHamilton Facility in Hamilton, MT 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Issuance of environmental 

assessment and finding of no significant 

impact for license amendment. 

FOR FURTHER INFORMATION CONTACT: 

Janine F. Katanic, Ph.D., Health 

Physicist, Nuclear Materials Inspection 

Branch, Division of Nuclear Materials 

Safety, Region IV, U.S. Nuclear 

Regulatory Commission, 611 Ryan Plaza 

Drive, Suite 400, Arlington, Texas 

76011; telephone: (817) 860–8151; fax 

number: (817) 860–8188; or by e-mail: 

jfk@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. 25–

19852–01. The license is held by 

GlaxoSmithKline Biologicals-Hamilton 

(the Licensee), for its Hamilton facility 

(the Facility), located at 553 Old 

Corvallis Road in Hamilton, Montana. 

Issuance of the amendment would 

authorize release of Building 7 of the 

Facility for unrestricted use. The 

Licensee requested this action in a letter 

dated June 8, 2006. 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 June 8, 2006, license 

amendment request, resulting in the 

release of Building 7 of the Facility for 

unrestricted use. License No. 25–19852–

01 was issued on June 24, 1988, 

pursuant to 10 CFR Part 30, and has 

been amended periodically since that 

time. This license authorizes the 

Licensee to possess and use small 

quantities of byproduct material, in both 

sealed and unsealed form, for laboratory 

research in immunological and 

biochemical studies. Additionally, the 

license authorizes the Licensee to 

possess and use a self-shielded 

irradiator device and to possess and use 

sealed sources for the purposes of 

performing instrument calibration. 

The Facility is situated on 35 acres 

(14 hectares) and consists of a main 

building comprised of office space and 

laboratories as well as several smaller 

buildings used for various purposes. 

The Facility is located in a mixed 

residential/commercial area. The 

Licensee’s June 8, 2006, license 

amendment request specifically 

addressed the release of Building 7 of 

the Facility for unrestricted use. 

Building 7 was constructed of filled 

concrete block walls set on a concrete 

floor, and its dimensions were 30 feet 

(9.1 meters) long by 15 feet (4.6 meters) 

wide and 8 feet (2.4 meters) in height. 

The building had a filled concrete block 

wall down the center which separated 

the building into an East Room and a 

West Room. Each room had a separate 

entry door on the south side of the 

building. Within Building 7, licensed 

materials were confined to the East 

Room. The East Room was an area of 

approximately 15 feet (4.6 meters) by 13 

feet (4 meters) and had been used by the 

Licensee for the storage of licensed 

materials. 

On May 30, 2006, the Licensee ceased 

licensed activities in Building 7 and 

initiated a survey and decontamination 

of the East Room of Building 7. Based 

on the Licensee’s historical knowledge 

of the site and the conditions of the East 

Room of Building 7, the Licensee 

determined that only routine 

decontamination activities, in 

accordance with their radiation safety 

procedures, were required. The Licensee 

was not required to submit a 

decommissioning plan to the NRC. The 

Licensee conducted surveys of the East 

Room of Building 7 and provided 

information to the NRC to demonstrate 

that it meets the criteria in Subpart E of 

10 CFR Part 20 for unrestricted release. 

Need for the Proposed Action 

The Licensee has ceased conducting 

licensed activities in Building 7 of the 

Facility and seeks the unrestricted use 

of Building 7. 

Environmental Impacts of the Proposed 

Action 

The historical review of licensed 

activities conducted at Building 7 of the 

Facility shows that such activities 

involved use of the following 

radionuclides with half-lives greater 

than 120 days: hydrogen-3, carbon-14, 

and calcium-45. Prior to performing the 

final status survey, the Licensee 

conducted decontamination activities, 

as necessary, in the areas of Building 7 

affected by these radionuclides. 

The Licensee conducted a final status 

survey during May-June 2006. This 

survey covered the East Room of 

Building 7. The final status survey 

report was attached to the Licensee’s 

amendment request dated June 8, 2006. 

NRC regulation 10 CFR 20.1402, 

Radiological Criteria for Unrestricted 

Use, states in part that a site will be 

considered acceptable for unrestricted 

use if the residual radioactivity that is 

distinguishable from background 

radiation results in a total effective dose 

equivalent not to exceed 25 millirems 

per year (0.25 milliSeiverts per year) to 

an average member of the critical group 

(the group of individuals reasonably 

expected to receive the greatest 

exposure to residual radioactivity for 

any applicable set of circumstances). 

The Licensee elected to demonstrate 

compliance with the radiological 

criteria for unrestricted release as 

specified in 10 CFR 20.1402 by 

referencing Regulatory Guide 1.86, 

Table 1, Acceptable Surface 

Contamination Levels, and NUREG–

1556, Volume 11, Table S.5, Acceptable 

Surface Contamination Levels. Both 

tables provide a maximum 

contamination limit for uncontrolled 

release of facilities. Because these 

values were not dose-based calculations 

as required by the license termination 

rule in 10 CFR Part 20, they were 

compared to the screening values 

documented in NUREG–1757, Volume 

1, Revision 1, Consolidated NMSS 


pwalker on PROD1PC71 with NOTICES