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