Draft Regulatory Guide: Issuance, Availability, 40629-40630 [E9-19295]

Download as PDF Federal Register / Vol. 74, No. 154 / Wednesday, August 12, 2009 / Notices jlentini on DSKJ8SOYB1PROD with NOTICES STEM degree completion, and career choices. Research and demonstration projects also investigate effective practices for transitioning students with disabilities across critical academic junctures, retaining students in undergraduate and graduate STEM degree programs, and graduating students with STEM associate, baccalaureate and graduate degrees. Research, demonstration, and enrichment project results inform the delivery of innovative, transformative and successful practices employed by the Alliances for Students with Disabilities in STEM to increase the number of students with disabilities completing associate, undergraduate and graduate degrees in STEM and to increase the number of students with disabilities entering our nation’s science and engineering workforce. RDE projects contribute to closing the gaps occurring for people with disabilities in STEM fields by successfully disseminating findings, project evaluation results, and proven good practices and products to the public. The original information collection, approved by OMB in 1996, surveyed three groups of students: students with disabilities in STEM fields, student with disabilities in other fields, and students without disabilities in STEM fields. These data allowed NSFD to understand more fully the population of students with disabilities in STEM fields and the issues they faced. The collection that will be submitted for reinstatement focuses more specifically on the outcomes of the RDE program, and how alliances and researchers receiving NSF RDE funding have improved the academic environment for students with disabilities. This information collection will consist of an on-line data instrument that RDE awardees will use to submit annual data on their project activities and participants, as well as future evaluation activities. Use of the Information This information is required for effective administration, communication, program and project monitoring and evaluation, and for measuring attainment of NSF’s program, project and strategic goals, as required by the President’s Management agenda as represented by the Office of Management and Budget’s (OMB) Program Assessment Rating Tool (PART) and the NSF’s Strategic Plan. The Foundation’s FY 2006–2011 Strategic Plan describes four strategic outcome goals of Discovery, Learning, Research Infrastructure, and Stewardship. NSF’s complete strategic plan may be found at: https:// VerDate Nov<24>2008 16:38 Aug 11, 2009 Jkt 217001 www.nsf.gov/publications/ pubsumm.jsp?ods_key=nsf0648. Data collected will be used for accountability purposes, including responding from queries from Committees of Visitors and other scientific experts, and for separate research and evaluation studies. Estimate of Burden Respondents: Principal Investigators and/or project staff receiving NSF RDE awards. Number of Respondents: 45. Estimated Total Annual Burden on Respondents: 1220 hours. Frequency of Responses: Data will be collected from awardees annually, and on an as-needed basis for future evaluation work. Dated: August 7, 2009. Suzanne H. Plimpton, Reports Clearance Officer, National Science Foundation. [FR Doc. E9–19343 Filed 8–11–09; 8:45 am] BILLING CODE 7555–01–P 40629 examined, and/or copied for a fee, at the NRC’s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet 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 the documents located in ADAMS should contact the NRC PDR Reference staff by telephone at 1–800– 397–4209, or 301–415–4737 or by e-mail to pdr.resource@nrc.gov. Dated at Rockville, Maryland, this 5th day of August 2009. For the Nuclear Regulatory Commission. Jon H. Thompson, Project Manager, Plant Licensing Branch 2– 1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E9–19296 Filed 8–11–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [NRC–2009–0074; Docket No. 50–414] Duke Energy Carolinas, LLC; Notice of Withdrawal of Application for Amendment to Facility Operating License The U.S. Nuclear Regulatory Commission (the Commission) has granted the request of Duke Energy Carolinas, LLC (the licensee) to withdraw its November 20, 2008, application, as supplemented by letter dated February 26, 2009, for proposed amendment to Facility Operating License No. 50–414 for Catawba Nuclear Station, Unit 2 (Catawba 2), located in York County, South Carolina. The proposed amendment would have updated the leak-before-break evaluation for Catawba 2 and made associated updates to the Updated Final Safety Analysis Report for this unit. The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on February 24, 2009 (74 FR 8273). However, by letter dated March 31, 2009, the licensee withdrew the proposed change. For further details with respect to this action, see the application for amendment dated November 20, 2008, the supplement to the amendment dated February 26, 2009, and the licensee’s letter dated March 31, 2009, which withdrew the application for license amendment. Documents may be PO 00000 Frm 00069 Fmt 4703 Sfmt 4703 NUCLEAR REGULATORY COMMISSION [NRC–2009–0351] Draft Regulatory Guide: Issuance, Availability AGENCY: Nuclear Regulatory Commission. ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, DG–1236, ‘‘Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants.’’ FOR FURTHER INFORMATION CONTACT: Jonathan Ortega-Luciano, U. S. Nuclear Regulatory Commission, Washington, DC 20555–0001, telephone: (301) 415– 1159 or e-mail Jonathan.OrtegaLuciano@nrc.gov. SUPPLEMENTARY INFORMATION: I. Introduction The U.S. Nuclear Regulatory Commission (NRC) is issuing for public comment a draft guide in the agency’s ‘‘Regulatory Guide’’ series. This series was developed to describe and make available to the public such information as methods that are acceptable to the NRC staff for implementing specific parts of the NRC’s regulations, techniques that the staff uses in evaluating specific problems or postulated accidents, and data that the E:\FR\FM\12AUN1.SGM 12AUN1 40630 Federal Register / Vol. 74, No. 154 / Wednesday, August 12, 2009 / Notices jlentini on DSKJ8SOYB1PROD with NOTICES staff needs in its review of applications for permits and licenses. The draft regulatory guide (DG), entitled, ‘‘Initial Startup Test Program to Demonstrate Remote Shutdown Capability for Water-Cooled Nuclear Power Plants,’’ is temporarily identified by its task number, DG–1236, which should be mentioned in all related correspondence. DG–1236 is proposed Revision 2 of Regulatory Guide 1.68.2, dated July 1978. This guide describes an initial startup test program acceptable to the NRC staff for demonstrating hot shutdown capability and the potential for cold shutdown from outside the control room. This guide is applicable to watercooled nuclear power plants. Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 50), ‘‘Domestic Licensing of Production and Utilization Facilities,’’ and 10 CFR Part 52, ‘‘Licenses, Certifications, and Approvals for Nuclear Power Plants,’’ 10 CFR 50.34, ‘‘Contents of Applications; Technical Information,’’ and 10 CFR 52.79, ‘‘Contents of Application, Technical Information in FSAR,’’ require, in part, that an applicant for a license to operate a production or utilization facility provide a safety analysis report (SAR) that includes the principal design criteria for the proposed facility. The introduction to Appendix A, ‘‘General Design Criteria for Nuclear Power Plants,’’ to 10 CFR Part 50 states that these principal design criteria are to establish the necessary design, fabrication, construction, testing, and performance requirements for structures, systems, and components (SSCs) important to safety (i.e., SSCs that provide reasonable assurance that the facility can be operated without undue risk to the health and safety of the public). II. Further Information The NRC staff is soliciting comments on DG–1236. Comments may be accompanied by relevant information or supporting data and should mention DG–1236 in the subject line. Comments submitted in writing or in electronic form will be made available to the public in their entirety through the NRC’s Agencywide Documents Access and Management System (ADAMS). Because your comments will not be edited to remove any identifying or contact information, the NRC cautions you against including any information in your submission that you do not want to be publicly disclosed. The NRC requests that any party soliciting or aggregating comments received from other persons for VerDate Nov<24>2008 16:38 Aug 11, 2009 Jkt 217001 submission to the NRC inform those persons that the NRC will not edit their comments to remove any identifying or contact information, and therefore, they should not include any information in their comments that they do not want publicly disclosed. You may submit comments by any of the following methods: 1. Mail comments to: Rulemaking and Directives Branch, Mail Stop: TWB–05– B01M, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001. 2. Federal e-Rulemaking Portal: Go to https://www.regulations.gov and search for documents filed under Docket ID [NRC–2009–0351]. Address questions about NRC dockets to Carol Gallagher, 301–492–3668; e-mail Carol.Gallagher@nrc.gov. 3. Fax comments to: Rulemaking and Directives Branch, Office of Administration, U.S. Nuclear Regulatory Commission at (301) 492–3446. Requests for technical information about DG–1236 may be directed to the NRC contact, Jonathan Ortega-Luciano at (301) 251–7627 or e-mail to Jonathan.Ortega-Luciano@nrc.gov. Comments would be most helpful if received by October 9, 2009. Comments received after that date will be considered if it is practical to do so, but the NRC is able to ensure consideration only for comments received on or before this date. Although a time limit is given, comments and suggestions in connection with items for inclusion in guides currently being developed or improvements in all published guides are encouraged at any time. Electronic copies of DG–1236 are available through the NRC’s public Web site under Draft Regulatory Guides in the ‘‘Regulatory Guides’’ collection of the NRC’s Electronic Reading Room at https://www.nrc.gov/reading-rm/doccollections/. Electronic copies are also available in ADAMS (https:// www.nrc.gov/reading-rm/adams.html), under Accession No. ML091210435. In addition, regulatory guides are available for inspection at the NRC’s Public Document Room (PDR) located at 11555 Rockville Pike, Rockville, Maryland. The PDR’s mailing address is USNRC PDR, Washington, DC 20555– 0001. The PDR can also be reached by telephone at (301) 415–4737 or (800) 397–4205, by fax at (301) 415–3548, and by e-mail to pdr.resource@nrc.gov. Regulatory guides are not copyrighted, and Commission approval is not required to reproduce them. Dated at Rockville, Maryland, this 4th day of August, 2009. PO 00000 Frm 00070 Fmt 4703 Sfmt 4703 For the Nuclear Regulatory Commission. John N. Ridgely, Acting Chief, Regulatory Guide Development Branch, Division of Engineering, Office of Nuclear Regulatory Research. [FR Doc. E9–19295 Filed 8–11–09; 8:45 am] BILLING CODE 7590–01–P NUCLEAR WASTE TECHNICAL REVIEW BOARD Notice of Meeting Board meeting: September 23, 2009– National Harbor, MD; the U.S. Nuclear Waste Technical Review Board will meet to discuss the implications of fuelcycle technologies for nuclear waste management and disposal. Pursuant to its authority under section 5051 of Public Law 100–203, Nuclear Waste Policy Amendments Act of 1987, the U.S. Nuclear Waste Technical Review Board will meet at National Harbor, Maryland, on Wednesday, September 23, 2009, to discuss the implications of alternative technological strategies for the management and disposal of spent nuclear fuel and high-level radioactive waste. The Board will receive an update on the Fuel Cycle Study being conducted at the Massachusetts Institute of Technology, and a panel of industry representatives will discuss their proposals to the U.S. Department of Energy (DOE) for recycling, reprocessing, and burning spent nuclear fuel in fast reactors. The Board also has invited a representative of the Nuclear Energy Agency to present an overview of efforts in other countries to manage and dispose of nuclear waste. Information presented at the meeting will be used by the Board as part of its ongoing effort to inform Congress, the Secretary of Energy, and a blue-ribbon commission of technical issues and questions that should be addressed related to waste-management alternatives. The Nuclear Waste Policy Amendments Act of 1987 requires the Board to conduct an independent review of the technical and scientific validity of DOE activities related to nuclear waste management, including transporting, packaging, and disposing of spent nuclear fuel and high-level radioactive waste. The Board meeting will be held at the Gaylord Hotel; 201 Waterfront Street; National Harbor, MD 20745; (tel.) 301– 965–2000, (fax) 301–965–2039. A detailed meeting agenda will be available on the Board’s Web site, http: //www.nwtrb.gov, approximately one week before the meeting. The agenda also may be obtained by telephone E:\FR\FM\12AUN1.SGM 12AUN1

Agencies

[Federal Register Volume 74, Number 154 (Wednesday, August 12, 2009)]
[Notices]
[Pages 40629-40630]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-19295]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[NRC-2009-0351]


Draft Regulatory Guide: Issuance, Availability

AGENCY: Nuclear Regulatory Commission.

ACTION: Notice of Issuance and Availability of Draft Regulatory Guide, 
DG-1236, ``Initial Startup Test Program to Demonstrate Remote Shutdown 
Capability for Water-Cooled Nuclear Power Plants.''

-----------------------------------------------------------------------

FOR FURTHER INFORMATION CONTACT: Jonathan Ortega-Luciano, U. S. Nuclear 
Regulatory Commission, Washington, DC 20555-0001, telephone: (301) 415-
1159 or e-mail Jonathan.Ortega-Luciano@nrc.gov.

SUPPLEMENTARY INFORMATION: 

I. Introduction

    The U.S. Nuclear Regulatory Commission (NRC) is issuing for public 
comment a draft guide in the agency's ``Regulatory Guide'' series. This 
series was developed to describe and make available to the public such 
information as methods that are acceptable to the NRC staff for 
implementing specific parts of the NRC's regulations, techniques that 
the staff uses in evaluating specific problems or postulated accidents, 
and data that the

[[Page 40630]]

staff needs in its review of applications for permits and licenses.
    The draft regulatory guide (DG), entitled, ``Initial Startup Test 
Program to Demonstrate Remote Shutdown Capability for Water-Cooled 
Nuclear Power Plants,'' is temporarily identified by its task number, 
DG-1236, which should be mentioned in all related correspondence. DG-
1236 is proposed Revision 2 of Regulatory Guide 1.68.2, dated July 
1978.
    This guide describes an initial startup test program acceptable to 
the NRC staff for demonstrating hot shutdown capability and the 
potential for cold shutdown from outside the control room. This guide 
is applicable to water-cooled nuclear power plants.
    Title 10, Part 50, of the Code of Federal Regulations (10 CFR Part 
50), ``Domestic Licensing of Production and Utilization Facilities,'' 
and 10 CFR Part 52, ``Licenses, Certifications, and Approvals for 
Nuclear Power Plants,'' 10 CFR 50.34, ``Contents of Applications; 
Technical Information,'' and 10 CFR 52.79, ``Contents of Application, 
Technical Information in FSAR,'' require, in part, that an applicant 
for a license to operate a production or utilization facility provide a 
safety analysis report (SAR) that includes the principal design 
criteria for the proposed facility. The introduction to Appendix A, 
``General Design Criteria for Nuclear Power Plants,'' to 10 CFR Part 50 
states that these principal design criteria are to establish the 
necessary design, fabrication, construction, testing, and performance 
requirements for structures, systems, and components (SSCs) important 
to safety (i.e., SSCs that provide reasonable assurance that the 
facility can be operated without undue risk to the health and safety of 
the public).

II. Further Information

    The NRC staff is soliciting comments on DG-1236. Comments may be 
accompanied by relevant information or supporting data and should 
mention DG-1236 in the subject line. Comments submitted in writing or 
in electronic form will be made available to the public in their 
entirety through the NRC's Agencywide Documents Access and Management 
System (ADAMS).
    Because your comments will not be edited to remove any identifying 
or contact information, the NRC cautions you against including any 
information in your submission that you do not want to be publicly 
disclosed.
    The NRC requests that any party soliciting or aggregating comments 
received from other persons for submission to the NRC inform those 
persons that the NRC will not edit their comments to remove any 
identifying or contact information, and therefore, they should not 
include any information in their comments that they do not want 
publicly disclosed. You may submit comments by any of the following 
methods:
    1. Mail comments to: Rulemaking and Directives Branch, Mail Stop: 
TWB-05-B01M, Division of Administrative Services, Office of 
Administration, U.S. Nuclear Regulatory Commission, Washington, DC 
20555-0001.
    2. Federal e-Rulemaking Portal: Go to https://www.regulations.gov 
and search for documents filed under Docket ID [NRC-2009-0351]. Address 
questions about NRC dockets to Carol Gallagher, 301-492-3668; e-mail 
Carol.Gallagher@nrc.gov.
    3. Fax comments to: Rulemaking and Directives Branch, Office of 
Administration, U.S. Nuclear Regulatory Commission at (301) 492-3446.
    Requests for technical information about DG-1236 may be directed to 
the NRC contact, Jonathan Ortega-Luciano at (301) 251-7627 or e-mail to 
Jonathan.Ortega-Luciano@nrc.gov.
    Comments would be most helpful if received by October 9, 2009. 
Comments received after that date will be considered if it is practical 
to do so, but the NRC is able to ensure consideration only for comments 
received on or before this date. Although a time limit is given, 
comments and suggestions in connection with items for inclusion in 
guides currently being developed or improvements in all published 
guides are encouraged at any time.
    Electronic copies of DG-1236 are available through the NRC's public 
Web site under Draft Regulatory Guides in the ``Regulatory Guides'' 
collection of the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/doc-collections/. Electronic copies are also available in 
ADAMS (https://www.nrc.gov/reading-rm/adams.html), under Accession No. 
ML091210435.
    In addition, regulatory guides are available for inspection at the 
NRC's Public Document Room (PDR) located at 11555 Rockville Pike, 
Rockville, Maryland. The PDR's mailing address is USNRC PDR, 
Washington, DC 20555-0001. The PDR can also be reached by telephone at 
(301) 415-4737 or (800) 397-4205, by fax at (301) 415-3548, and by e-
mail to pdr.resource@nrc.gov.
    Regulatory guides are not copyrighted, and Commission approval is 
not required to reproduce them.

    Dated at Rockville, Maryland, this 4th day of August, 2009.

    For the Nuclear Regulatory Commission.
John N. Ridgely,
Acting Chief, Regulatory Guide Development Branch, Division of 
Engineering, Office of Nuclear Regulatory Research.
[FR Doc. E9-19295 Filed 8-11-09; 8:45 am]
BILLING CODE 7590-01-P
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