Omaha Public Power District; Notice of Denial of Amendment to Facility Operating License and Opportunity for Hearing, 57075-57076 [07-4939]

Download as PDF Federal Register / Vol. 72, No. 193 / Friday, October 5, 2007 / Notices 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 yshivers on PROD1PC62 with NOTICES 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 VerDate Aug<31>2005 15:33 Oct 04, 2007 Jkt 214001 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 PO 00000 Frm 00095 Fmt 4703 Sfmt 4703 57075 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. E:\FR\FM\05OCN1.SGM 05OCN1 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 Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact for License Amendment. AGENCY: FOR FURTHER INFORMATION CONTACT: yshivers on PROD1PC62 with NOTICES 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 VerDate Aug<31>2005 15:33 Oct 04, 2007 Jkt 214001 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. PO 00000 Frm 00096 Fmt 4703 Sfmt 4703 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 E:\FR\FM\05OCN1.SGM 05OCN1

Agencies

[Federal Register Volume 72, Number 193 (Friday, October 5, 2007)]
[Notices]
[Pages 57075-57076]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 07-4939]


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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 e-mail 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.


[[Page 57076]]


    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