Federal Register / Vol. 72, No. 193 / Friday, October 5, 2007 / Notices 57075 

and the Planning for the Minority 

Technical Organization Summit has 

been added. 

• The Report on the NSF Broadening 

Participation Plan has been moved to 

October 17. 

Contact Person: Dr. Margaret E.M. 

Tolbert, Senior Advisor and Executive 

Liaison, CEOSE, Office of Integrative 

Activities, National Science Foundation, 

4201 Wilson Boulevard Arlington, VA 

22230, Telephone: (703) 292–8040, 

mtolbert@nsf.gov. 

Agenda 

Tuesday, October 16, 2007 

Welcome and Opening Statement by the 

CEOSE Chair 

Introductions 

Presentations and Discussions: 

• Experimental Program to Stimulate 

Competitive Research 

• Broadening Participation Briefings 

on NSF Advisory Committee 

Meetings 

• Planning for the Minority Technical 

Organization Summit 

• Concurrent Planning Meetings of 

CEOSE Ad Hoc Subcommittees 

• Reports on Strategic Planning by 

CEOSE, Mini-Symposium: 

Institutions Serving Persons with 

Disabilities Who Are in STEM 

Fields, and Broadening 

Participation Efforts of Several 

Federal Agencies 

Wednesday, October 17, 2007 

Opening Statement by the New CEOSE 

Chair 

Presentations/Discussions: 

• Report on the NSF Broadening 

Participation Plan 

• Broadening Participation Initiatives 

of the NSF Directorate for 

Engineering 

• Broadening Participation Initiatives 

of the Chemistry Division of the 

NSF Directorate for Mathematical 

and Physical Sciences 

• Discussion Topics Pertinent to the 

CEOSE Mandate with the NSF 

Director and Deputy Director 

Completion of Unfinished Business 

Dated: October 1, 2007. 

Susanne Bolton, 

Committee Management Officer. 

[FR Doc. E7–19656 Filed 10–4–07; 8:45 am] 

BILLING CODE 7555–01–P 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 50–285] 

Omaha Public Power District; Notice of 

Denial of Amendment to Facility 

Operating License and Opportunity for 

Hearing 

The U.S. Nuclear Regulatory 

Commission (NRC or the Commission) 

has denied a request by Omaha Public 

Power District (the licensee), for an 

amendment to Renewed Facility 

Operating License No. DPR–40 issued to 

the licensee for operation of the Fort 

Calhoun Station, Unit No. 1, located in 

Washington County, Nebraska. 

Notice of Consideration of Issuance of 

this amendment was published in the 

Federal Register on April 26, 2005 (70 

FR 21459). 

By letter dated March 31, 2005, the 

licensee requested an amendment to 

revise the Renewed Facility Operating 

License and Technical Specifications 

(TSs) to increase the license core power. 

Fort Calhoun Station, Unit No. 1, is 

currently licensed for a rated thermal 

power of 1500 megawatts thermal 

(MWt). Through the use of more 

accurate feedwater flow measurement 

equipment, approval was sought to 

increase this core power by 1.5 percent 

to 1522 MWt. The power uprate would 

be based on the use of the 

CROSSFLOWTM system for 

determination of main feedwater flow 

and the associated determination of 

reactor power through the performance 

of the power calorimetric currently 

required by the Fort Calhoun Station 

TSs. 

The OPPD license amendment request 

to increase core power is based on 

Westinghouse topical report CENPD–

397–P–A, ‘‘Improved Flow 

Measurement Accuracy Using Crossflow 

Ultrasonic Flow Measurement 

Technology,’’ for new and future uses of 

the CROSSFLOW ultrasonic flow meter. 

The topical report provided several 

assessments with respect to that topical 

report to justify the power increase. 

Because the licensee’s license 

amendment request is based on CENPD–

397–P–A and the NRC staff has 

suspended its approval, as explained in 

the NRC staff’s letter to Westinghouse 

dated September 26, 2007, of the use of 

this topical report in license amendment 

requests, the NRC staff has concluded 

that the licensee’s request cannot be 

granted. The licensee was notified of the 

Commission’s denial of the proposed 

change by a letter dated September 27, 

2007. 

By 30 days from the date of 

publication of this notice in the Federal 

Register, the licensee may demand a 

hearing with respect to the denial 

described above. Any person whose 

interest may be affected by this 

proceeding may file a written petition 

for leave to intervene pursuant to the 

requirements of 10 CFR 2.309. 

A request for hearing or petition for 

leave to intervene must be filed with the 

Secretary of the Commission, U.S. 

Nuclear Regulatory Commission, 

Washington, DC 20555–0001 Attention: 

Rulemakings and Adjudications Staff, or 

may be delivered to the Commission’s 

Public Document Room (PDR), located 

at One White Flint North, Public File 

Area O1 F21, 11555 Rockville Pike (first 

floor), Rockville, Maryland, by the 

above date. A request for hearing or 

petition for leave to intervene may also 

be transmitted directly to the Secretary 

of the Commission by means of 

facsimile transmission to 301–415–1101 

or by e-mail to hearingdocket@nrc.gov. 

A copy of any petitions should also be 

sent to the Office of the General 

Counsel, U.S. Nuclear Regulatory 

Commission, Washington, DC 20555–

0001. Copies of petitions may also be 

transmitted directly to the Office of the 

General Counsel by means of facsimile 

transmission to 301–415–3725 or by email to OGCMailCenter@nrc.gov. A copy 

of any petitions should also be sent to 

James R. Curtiss, Esq., Winston & 

Strawn, 1700 K Street, NW., 

Washington, DC 20006–3817, Senior 

Counsel for the licensee. 

For further details with respect to this 

action, see (1) The application for 

amendment dated March 31, 2005, and 

(2) the Commission’s letter to the 

licensee dated September 27, 2007. 

Documents may be examined, and/or 

copied for a fee, at the NRC’s PDR, 

located at One White Flint North, Public 

File Area O1 F21, 11555 Rockville Pike 

(first floor), Rockville, Maryland, and 

will be accessible electronically through 

the Agencywide Documents Access and 

Management System’s (ADAMS) Public 

Electronic Reading Room link at the 

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

reading-rm/adams.html. Persons who 

do not have access to ADAMS or who 

encounter problems in accessing 

documents located in ADAMS should 

contact the NRC PDR Reference staff by 

telephone at 1–800–397–4209, 301–

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

Dated at Rockville, Maryland, this 27th day 

of September 2007. 


yshivers on PROD1PC62 with NOTICES
57076 Federal Register / Vol. 72, No. 193 / Friday, October 5, 2007 / Notices 

For the Nuclear Regulatory Commission. 

Timothy J. McGinty, 

Acting Director, Division of Operating Reactor 

Licensing Office of Nuclear Reactor 

Regulation. 

[FR Doc. 07–4939 Filed 10–4–07; 8:45 am] 

BILLING CODE 7590–01–M 

NUCLEAR REGULATORY 

COMMISSION 

[Docket No. 030–30292] 

Notice of Availability of Environmental 

Assessment and Finding of No 

Significant Impact for License 

Amendment to Byproduct, Materials 

License No. 06–13053–04, for 

Termination of the License and 

Unrestricted Release of Bayer 

Pharmaceuticals Corporation’s Facility 

in West Haven, CT 

AGENCY: Nuclear Regulatory 

Commission. 

ACTION: Issuance of Environmental 

Assessment and Finding of No 

Significant Impact for License 

Amendment. 

FOR FURTHER INFORMATION CONTACT: 

Dennis Lawyer, Health Physicist, 

Commercial and R&D Branch, Division 

of Nuclear Materials Safety, Region I, 

475 Allendale Road, King of Prussia, 

Pennsylvania; telephone 610–337–5366; 

fax number 610–337–5393; or by e-mail: 

drl1@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. 06–

13053–04. This license is held by Bayer 

Pharmaceuticals Corporation (the 

Licensee), for its Bayer Pharmaceuticals 

Corporation Facility located at 400 

Morgan Lane in West Haven, 

Connecticut (the Facility). Issuance of 

the amendment would authorize release 

of the Facility for unrestricted use and 

termination of the NRC license. The 

Licensee requested this action in a letter 

dated April 17, 2007, and responded to 

an information request by letters dated 

July 9, 2007, and August 6, 2007. 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 April 17, 2007, license 

amendment request, resulting in release 

of the Facility for unrestricted use and 

the termination of its NRC materials 

license. License No. 06–13053–04 was 

issued on December 2, 1987, pursuant to 

10 CFR part 30, and has been amended 

periodically since that time. Licensed 

activities at the Facility were also 

conducted under the following licenses 

during the dates indicated: License No. 

06–13053–01 (December 17, 1968 

through July 15, 1993); License No. 06–

20589–01 (April 20, 1983 through 

February 25, 1988); and License No. 06–

20972–01 (March 13, 1986 through 

February 5, 1988). These licenses were 

transferred to License No. 06–13053–04 

and terminated. These licenses 

authorized the Licensee to use unsealed 

byproduct material for purposes of 

conducting research and development 

activities typically on laboratory bench 

tops and in hoods. 

The Facility is situated on 137 acres 

and consists of office space and 

laboratories. The Facility is located in a 

mixed commercial industrial and 

residential area. Use of licensed 

materials was confined to five buildings 

within 30 acres and totaling 350,000 

square feet of building space. 

In January 2007, the Licensee ceased 

licensed activities and initiated a survey 

and decontamination 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 their NRCapproved, operating radiation safety 

procedures, were 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 

and the termination of its NRC materials 

license. Termination of its license 

would end the Licensee’s obligation to 

pay annual license fees to the NRC. 

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 radionuclides with halflives greater than 120 days: Hydrogen 3, 

carbon 14, chlorine 36, calcium 45, 

iodine 129, and gadolinium 153. Prior to 

performing the final status survey, the 

Licensee conducted decontamination 

activities, as necessary, in the areas of 

the Facility affected by these 

radionuclides. 

The Licensee conducted a final status 

survey January 3 through February 2, 

2007. The final status survey report was 

attached to the Licensee’s amendment 

request dated April 17, 2007, and letter 

dated July 9, 2007. 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 radionuclide-specific 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 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 NRCLicensed 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 


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