Notice of Docketing of Amendment Request for Material License SNM-2511; Pacific Gas and Electric Company; Diablo Canyon Independent Spent Fuel Storage Installation, 68638-68639 [E9-30618]
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68638
Federal Register / Vol. 74, No. 247 / Monday, December 28, 2009 / Notices
under investigation. Up to 16,660
respondents will be contacted across all
survey improvement projects. No
respondent will be contacted more than
twice in one year under this generic
clearance. Every effort will be made to
use technology to limit the burden on
respondents from small entities.
Both qualitative and quantitative
methods will be used to improve NSF’s
current data collection instruments and
processes and to reduce respondent
burden, as well as to develop new
surveys. Qualitative methods include,
but are not limited to, expert review;
exploratory, cognitive, and usability
interviews; focus groups; and
respondent debriefings. Cognitive and
usability interviews may include the use
of scenarios, paraphrasing, card sorts,
vignette classifications, and rating tasks.
Quantitative methods include, but are
not limited to, telephone surveys,
behavior coding, split panel tests, and
field tests.
Use of the Information. The purpose
of these studies is to use the latest and
most appropriate methodology to
improve NSF surveys. The data will be
used internally to improve NSF surveys.
Methodological findings may be
presented externally in technical papers
at conferences, published in the
proceedings of conferences, or in
journals. Improved NSF surveys will
help policy makers in decisions on
research and development funding,
graduate education, and the scientific
and technical workforce, as well as
contributing to reduced survey costs.
Burden on the Public. NSF estimates
that a total reporting and recordkeeping
burden of 14,950 hours will result from
activities to improve its surveys. The
calculation is shown in Table 1:
TABLE 1—ANTICIPATED SURVEYS TO UNDERTAKE IMPROVEMENT PROJECTS, ALONG WITH THE NUMBER OF
RESPONDENTS AND BURDEN HOURS PER SURVEY FOR THREE YEAR PERIOD
Number of
respondents 1
Survey name
Graduate Student Survey ........................................................................................................................................
SESTAT Surveys .....................................................................................................................................................
Postdoc Project ........................................................................................................................................................
New and Redesigned R&D Surveys.
Higher Education R&D .....................................................................................................................................
Government R&D .............................................................................................................................................
Nonprofit R&D ..................................................................................................................................................
Business R&D ..................................................................................................................................................
Microbusiness R&D ..........................................................................................................................................
Survey of Scientific & Engineering Facilities ...........................................................................................................
Public Understanding of S&E Surveys ....................................................................................................................
Survey of Earned Doctorates ..................................................................................................................................
Additional surveys not specified ..............................................................................................................................
2 1,500
Total ..................................................................................................................................................................
Hours
10,000
2,000
2,500
5,000
2,500
400
60
100
50
150
300
200
700
1,200
1,200
180
300
150
450
300
50
450
1,200
16,660
14,280
1 Number
of respondents listed for any individual survey may represent several methodological improvement projects.
number refers to the science, engineering, and health-related departments within the academic institutions of the United States (not the
academic institutions themselves).
erowe on DSK5CLS3C1PROD with NOTICES
2 This
Comments: Comments are invited on
(a) whether the proposed collection of
information is necessary for the proper
performance of the functions of the
Agency, including whether the
information shall have practical utility;
(b) the accuracy of the Agency’s
estimate of the burden of the proposed
collection of information; (c) ways to
enhance the quality, utility, and clarity
of the information on respondents,
including through the use of automated
collection techniques or other forms of
information technology; and (d) ways to
minimize the burden of the collection of
information on those who are to
respond, including through the use of
appropriate automated, electronic,
mechanical, or other technological
collection techniques or other forms of
information technology.
Comments submitted in response to
this notice will be summarized and/or
included in the request for OMB
approval of this information collection;
they also will become a matter of public
record.
VerDate Nov<24>2008
11:00 Dec 24, 2009
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Dated: December 22, 2009.
Suzanne Plimpton,
Reports Clearance Officer, National Science
Foundation.
[FR Doc. E9–30636 Filed 12–24–09; 8:45 am]
BILLING CODE 7555–01–P
Material Safety and Safeguards, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555–0001.
Telephone: (301) 492–3325; fax number:
(301) 492–3348; e-mail:
john.goshen@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
NUCLEAR REGULATORY
COMMISSION
[Docket No. 72–26; NRC–2009–0569]
Notice of Docketing of Amendment
Request for Material License SNM–
2511; Pacific Gas and Electric
Company; Diablo Canyon Independent
Spent Fuel Storage Installation
AGENCY: Nuclear Regulatory
Commission.
ACTION: Notice of Docketing of
Amendment Request for Materials
License SNM–2511.
FOR FURTHER INFORMATION CONTACT: John
Goshen, Project Manager, Licensing
Branch, Division of Spent Fuel Storage
and Transportation, Office of Nuclear
PO 00000
Frm 00073
Fmt 4703
Sfmt 4703
The U.S. Nuclear Regulatory
Commission (NRC or Commission) is
considering an application dated April
7, 2008, from Pacific Gas and Electric
Company (PG&E) to amend its Special
Nuclear Material License No. SNM–
2511, under the provisions of 10 CFR
Part 72, for the receipt, possession,
storage and transfer of spent fuel,
reactor-related Greater than Class C
waste and other radioactive materials
associated with spent fuel storage at the
Diablo Canyon Independent Spent Fuel
Storage Installation (ISFSI), located at
the Diablo Canyon Nuclear Power Plant,
Unit Nos. 1 and 2 site in San Luis
Obispo County, California. If granted,
the amendment will revise the technical
specifications (TS) as follows:
E:\FR\FM\28DEN1.SGM
28DEN1
erowe on DSK5CLS3C1PROD with NOTICES
Federal Register / Vol. 74, No. 247 / Monday, December 28, 2009 / Notices
1. Revise TS 3.1.1, ‘‘Multi-Purpose
Canister (MPC),’’ to clarify the required
helium leak rate condition and the leak
rate testing requirements;
2. Delete TS 3.1.4, ‘‘Spent Fuel
Storage Cask (SFSC) Time Limitation in
Cask Transfer Facility (CTF),’’ based on
analysis of the thermal performance of
the Holtec HI–STORM 100 system
which shows there is no need for a
required time limitation in the CTF;
3. Revise TS 3.2.1, ‘‘Dissolved Boron
Concentration,’’ to modify the dissolved
boron concentrations required for MPC–
32 canisters and, to allow linear
interpolation for some enrichments
consistent with the Holtec International
(Holtec) Certificate of Compliance (CoC)
No. 1014, Amendment 3, for the HI–
STORM 100 system;
4. Add a note to both surveillance
requirements of TS 3.2.1 to limit the
monitoring requirement consistent with
the Holtec CoC No. 1014, Amendment 1,
for the HI–STORM 100 system;
5. Revise TS 4.1.1.a, b, and c, ‘‘Design
Features Significant to Safety,’’ to allow
use of Metamic Boron-10 as a neutron
absorber for each of the specified MPC
consistent with Holtec CoC No.1014,
Amendment 2, for the HI–STORM 100
system, and add TS 4.1.2, ‘‘Design
Features Important to Criticality
Control,’’ to define the material and
testing requirements for the use of
Metamic;
6. Change the title of TS 4.3.4.a,
‘‘Permanent Load Handling
Equipment,’’ to ‘‘Weldment and
Reinforced Concrete,’’ which more
correctly reflect the subject of the TS
subparagraphs;
7. Revise TS 4.3.4.b, ‘‘Mobile Load
Handling Equipment,’’ to replace the
term ‘‘permanent load handling
equipment’’ with the term ‘‘the cask
transporter,’’ as the transporter is not
considered a mobile load handling
equipment within the context of TS
4.3.4.b; and
8. Revise item b of TS 5.1.3, ‘‘MPC
and SFSC Loading, Unloading, and
Preparation Program,’’ to clarify the
maintenance of the required conditions
in the annular gap between the MPC
and the transfer cask depending on
which drying process is used and fuel
heat load during MPC loading or
unloading operations.
This application was docketed under
10 CFR 72.16; the ISFSI Docket No. is
72–26 and will remain the same for this
action. The NRC inadvertently failed to
promptly publish this notice of
docketing in the Federal Register after
the NRC’s receipt of the PG&E April 7,
2008, license amendment request. All
other procedural requirements in Part
72 will be met as the NRC continues to
VerDate Nov<24>2008
11:00 Dec 24, 2009
Jkt 220001
process this license amendment request
(see section II of this notice,
‘‘Opportunity to Request a Hearing’’).
The Commission will approve the
license amendment if it determines that
the application meets the standards and
requirements of the Atomic Energy Act
of 1954, as amended (the Act) and the
Commission’s regulations, and pursuant
to 10 CFR 72.58, the findings required
by 10 CFR 72.40. These findings will be
documented in a Safety Evaluation
Report.
II. Opportunity To Request a Hearing
The Commission may issue either a
notice of hearing or a notice of proposed
action and opportunity for hearing in
accordance with 10 CFR 72.46(b)(1) or,
if a determination is made that the
amendment does not present a genuine
issue as to whether public health and
safety will be significantly affected, take
immediate action on the amendment in
accordance with 10 CFR 72.46(b)(2) and
provide notice of the action taken and
an opportunity for interested persons to
request a hearing on whether the action
should be rescinded or modified.
III. Further Information
Documents related to this action,
including the application for
amendment and supporting
documentation, are available
electronically at the NRC’s Electronic
Reading Room at https://www.nrc.gov/
reading-rm/adams.html. From this site,
you can access the NRC’s Agencywide
Document Access and Management
System (ADAMS), which provides text
and image files of NRC’s public
documents. The ADAMS accession
number for the document related to this
notice is ML081070073. If you do not
have access to ADAMS or if there are
problems in accessing the documents
located in ADAMS, contact the NRC
Public Document Room (PDR) Reference
staff at 1–800–397–4209, 301–415–4737
or by e-mail to pdr.resource@nrc.gov.
These documents may also be viewed
electronically on the public computers
located at the NRC’s PDR, O1 F21, One
White Flint North, 11555 Rockville
Pike, Rockville, MD 20852. The PDR
reproduction contractor will copy
documents for a fee.
Dated at Rockville, Maryland, this 15th day
of December 2009.
For The Nuclear Regulatory Commission.
John Goshen, P.E.,
Project Manager, Licensing Branch, Division
of Spent Fuel Storage and Transportation,
Office of Nuclear Material Safety and
Safeguards.
[FR Doc. E9–30618 Filed 12–24–09; 8:45 am]
BILLING CODE 7590–01–P
PO 00000
Frm 00074
Fmt 4703
Sfmt 4703
68639
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–361 and 50–362, NRC–
2009–0570]
Southern California Edison: San
Onofre Nuclear Generating Station,
Unit 2 and Unit 3 Temporary
Exemption
1.0
Background
Southern California Edison (SCE, the
licensee) is the holder of the Facility
Operating License Nos. NPF–10 and
NPF–15, which authorize operation of
the San Onofre Nuclear Generating
Station, Units 2 and 3 (SONGS 2 and 3),
respectively. The licenses provide,
among other things, that the facility is
subject to all rules, regulations, and
orders of the Nuclear Regulatory
Commission (NRC or the Commission)
now or hereafter in effect.
The facility consists of two
pressurized-water reactors (PWRs)
located in San Diego County, California.
2.0
Request/Action
Pursuant to Title 10 of the Code of
Federal Regulations (10 CFR), Section
50.12, ‘‘Specific exemptions,’’ SCE has,
by letter dated January 30, 2009, as
supplemented by letters dated March 16
and September 29, 2009 (Agencywide
Documents Access and Management
System (ADAMS) Accession Nos.
ML090360738, ML090780251, and
ML092740310, respectively), requested
a temporary exemption from 10 CFR
50.46, ‘‘Acceptance criteria for
emergency core cooling systems for
light-water nuclear power reactors,’’ and
Appendix K to 10 CFR 50, ‘‘ECCS
[emergency core cooling system]
Evaluation Models’’ (Appendix K). The
regulation in 10 CFR 50.46 contains
acceptance criteria for the ECCS for
light-water nuclear power reactors
fueled with uranium oxide pellets
within cylindrical zircaloy or ZIRLOTM
cladding. In addition, Appendix K to 10
CFR Part 50 requires that the Baker-Just
equation be used to predict the rates of
energy release, hydrogen concentration,
and cladding oxidation from the metalwater reaction in the development and
application of an acceptable ECCS
model. The temporary exemption
request relates solely to the specific
types of cladding material specified in
these regulations. As written, the
regulations require the use of zircaloy or
ZIRLOTM fuel rod cladding. Thus, SCE
needs an exemption from the
requirements of 10 CFR 50.46, and
Appendix K in order to use (irradiate)
lead fuel assemblies (LFAs) with a
different cladding material, M5 alloy, at
E:\FR\FM\28DEN1.SGM
28DEN1
]]>Agencies
[Federal Register Volume 74, Number 247 (Monday, December 28, 2009)]
[Notices]
[Pages 68638-68639]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-30618]
=======================================================================
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket No. 72-26; NRC-2009-0569]
Notice of Docketing of Amendment Request for Material License
SNM-2511; Pacific Gas and Electric Company; Diablo Canyon Independent
Spent Fuel Storage Installation
AGENCY: Nuclear Regulatory Commission.
ACTION: Notice of Docketing of Amendment Request for Materials License
SNM-2511.
-----------------------------------------------------------------------
FOR FURTHER INFORMATION CONTACT: John Goshen, Project Manager,
Licensing Branch, Division of Spent Fuel Storage and Transportation,
Office of Nuclear Material Safety and Safeguards, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001. Telephone: (301) 492-
3325; fax number: (301) 492-3348; e-mail: john.goshen@nrc.gov.
SUPPLEMENTARY INFORMATION:
I. Introduction
The U.S. Nuclear Regulatory Commission (NRC or Commission) is
considering an application dated April 7, 2008, from Pacific Gas and
Electric Company (PG&E) to amend its Special Nuclear Material License
No. SNM-2511, under the provisions of 10 CFR Part 72, for the receipt,
possession, storage and transfer of spent fuel, reactor-related Greater
than Class C waste and other radioactive materials associated with
spent fuel storage at the Diablo Canyon Independent Spent Fuel Storage
Installation (ISFSI), located at the Diablo Canyon Nuclear Power Plant,
Unit Nos. 1 and 2 site in San Luis Obispo County, California. If
granted, the amendment will revise the technical specifications (TS) as
follows:
[[Page 68639]]
1. Revise TS 3.1.1, ``Multi-Purpose Canister (MPC),'' to clarify
the required helium leak rate condition and the leak rate testing
requirements;
2. Delete TS 3.1.4, ``Spent Fuel Storage Cask (SFSC) Time
Limitation in Cask Transfer Facility (CTF),'' based on analysis of the
thermal performance of the Holtec HI-STORM 100 system which shows there
is no need for a required time limitation in the CTF;
3. Revise TS 3.2.1, ``Dissolved Boron Concentration,'' to modify
the dissolved boron concentrations required for MPC-32 canisters and,
to allow linear interpolation for some enrichments consistent with the
Holtec International (Holtec) Certificate of Compliance (CoC) No. 1014,
Amendment 3, for the HI-STORM 100 system;
4. Add a note to both surveillance requirements of TS 3.2.1 to
limit the monitoring requirement consistent with the Holtec CoC No.
1014, Amendment 1, for the HI-STORM 100 system;
5. Revise TS 4.1.1.a, b, and c, ``Design Features Significant to
Safety,'' to allow use of Metamic Boron-10 as a neutron absorber for
each of the specified MPC consistent with Holtec CoC No.1014, Amendment
2, for the HI-STORM 100 system, and add TS 4.1.2, ``Design Features
Important to Criticality Control,'' to define the material and testing
requirements for the use of Metamic;
6. Change the title of TS 4.3.4.a, ``Permanent Load Handling
Equipment,'' to ``Weldment and Reinforced Concrete,'' which more
correctly reflect the subject of the TS subparagraphs;
7. Revise TS 4.3.4.b, ``Mobile Load Handling Equipment,'' to
replace the term ``permanent load handling equipment'' with the term
``the cask transporter,'' as the transporter is not considered a mobile
load handling equipment within the context of TS 4.3.4.b; and
8. Revise item b of TS 5.1.3, ``MPC and SFSC Loading, Unloading,
and Preparation Program,'' to clarify the maintenance of the required
conditions in the annular gap between the MPC and the transfer cask
depending on which drying process is used and fuel heat load during MPC
loading or unloading operations.
This application was docketed under 10 CFR 72.16; the ISFSI Docket
No. is 72-26 and will remain the same for this action. The NRC
inadvertently failed to promptly publish this notice of docketing in
the Federal Register after the NRC's receipt of the PG&E April 7, 2008,
license amendment request. All other procedural requirements in Part 72
will be met as the NRC continues to process this license amendment
request (see section II of this notice, ``Opportunity to Request a
Hearing'').
The Commission will approve the license amendment if it determines
that the application meets the standards and requirements of the Atomic
Energy Act of 1954, as amended (the Act) and the Commission's
regulations, and pursuant to 10 CFR 72.58, the findings required by 10
CFR 72.40. These findings will be documented in a Safety Evaluation
Report.
II. Opportunity To Request a Hearing
The Commission may issue either a notice of hearing or a notice of
proposed action and opportunity for hearing in accordance with 10 CFR
72.46(b)(1) or, if a determination is made that the amendment does not
present a genuine issue as to whether public health and safety will be
significantly affected, take immediate action on the amendment in
accordance with 10 CFR 72.46(b)(2) and provide notice of the action
taken and an opportunity for interested persons to request a hearing on
whether the action should be rescinded or modified.
III. Further Information
Documents related to this action, including the application for
amendment and supporting documentation, are available electronically at
the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. From this site, you can access the NRC's Agencywide
Document Access and Management System (ADAMS), which provides text and
image files of NRC's public documents. The ADAMS accession number for
the document related to this notice is ML081070073. If you do not have
access to ADAMS or if there are problems in accessing the documents
located in ADAMS, contact the NRC Public Document Room (PDR) Reference
staff at 1-800-397-4209, 301-415-4737 or by e-mail to
pdr.resource@nrc.gov.
These documents may also be viewed electronically on the public
computers located at the NRC's PDR, O1 F21, One White Flint North,
11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction
contractor will copy documents for a fee.
Dated at Rockville, Maryland, this 15th day of December 2009.
For The Nuclear Regulatory Commission.
John Goshen, P.E.,
Project Manager, Licensing Branch, Division of Spent Fuel Storage and
Transportation, Office of Nuclear Material Safety and Safeguards.
[FR Doc. E9-30618 Filed 12-24-09; 8:45 am]
BILLING CODE 7590-01-P
