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]

Download as PDF 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 Jkt 220001 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 http://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]


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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 http://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