Advisory Committee on Reactor Safeguards Renewal, 75595 [2014-29194]

Download as PDF Federal Register / Vol. 79, No. 243 / Thursday, December 18, 2014 / Notices number, expiration date and country of issue; and employer/affiliation information (name of institution, address, country, telephone, email, phone). Contact the International Visitor Coordinator, Mary Treat, at (228) 688– 3916 for the specifics on any foreign national visitors. To expedite admittance, attendees with U.S. citizenship and Permanent Residents (green card holders) can provide identifying information 3 working days in advance by emailing the NASA Office of Communications at SSC–PAO@ mail.nasa.gov. It is imperative that the meeting be held on these dates to accommodate the scheduling priorities of the key participants. Patricia D. Rausch, Advisory Committee Management Officer, National Aeronautics and Space Administration. BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Nuclear Regulatory Commission. ACTION: Exemption; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) is issuing an exemption in response to a July 17, 2013, request from Duke Energy Florida, Inc. (DEF or the licensee), from certain regulatory requirements. The exemption would remove the requirement that a licensed senior operator approve the emergency suspension of security measures for Crystal River Unit 3 Nuclear Generating Plant (CR3) during certain emergency conditions or during severe weather. DATES: December 18, 2014. ADDRESSES: Please refer to Docket ID NRC–2014–0266 when contacting the NRC about the availability of information regarding this document. You may obtain publicly available information related to this document using any of the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2014–0266. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may access publicly available documents online in the ADAMS Public Documents collection at http://www.nrc.gov/reading-rm/ adams.html. To begin the search, select ‘‘ADAMS Public Documents’’ and then select ‘‘Begin Web-based ADAMS Search.’’ For problems with ADAMS, please contact the NRC’s Public SUMMARY: NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards Renewal U.S. Nuclear Regulatory Commission. ACTION: Notice of renewal of the Charter of the Advisory Committee on Reactor Safeguards (ACRS). AGENCY: The Nuclear Regulatory Commission has determined that renewal of the charter for the ACRS until December 4, 2016, is in the public interest in connection with the statutory responsibilities assigned to the ACRS. This action is being taken in accordance with the Federal Advisory Committee Act. FOR FURTHER INFORMATION CONTACT: Andrew L. Bates, Office of the Secretary, NRC, Washington, DC 20555; by telephone: (301) 415–1963, or email at ALB@NRC.GOV. SUPPLEMENTARY INFORMATION: The Advisory Committee on Reactor Safeguards was established by Section 29 of the Atomic Energy Act (AEA) of 1954, as amended. Its purpose is to provide advice to the Commission with regard to the hazards of proposed or existing reactor facilities, to review each application for a construction permit or operating license for certain facilities specified in the AEA, and such other duties as the Commission may request. The AEA as amended by PL 100–456 also specifies that the Defense Nuclear Safety Board may obtain the advice and recommendations of the ACRS. SUMMARY: mstockstill on DSK4VPTVN1PROD with NOTICES [FR Doc. 2014–29194 Filed 12–17–14; 8:45 a.m.] Duke Energy Florida, Inc. BILLING CODE 7510–13–P 19:23 Dec 17, 2014 Dated: December 8, 2014. Andrew L. Bates, Advisory Committee Management Officer. [Docket No. 50–302; NRC–2014–0266] [FR Doc. 2014–29624 Filed 12–17–14; 8:45 am] VerDate Sep<11>2014 Membership on the Committee includes individuals experienced in reactor operations, management; probabilistic risk assessment; analysis of reactor accident phenomena; design of nuclear power plant structures, systems and components; materials science; and mechanical, civil, and electrical engineering. Jkt 235001 PO 00000 Frm 00065 Fmt 4703 Sfmt 4703 75595 Document Room (PDR) reference staff at 1–800–397–4209, 301–415–4737, or by email to pdr.resource@nrc.gov. The ADAMS accession number for each document referenced in this document (if that document is available in ADAMS) is provided the first time that a document is referenced. • NRC’s PDR: You may examine and purchase copies of public documents at the NRC’s PDR, Room O1–F21, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Michael Orenak, Office of Nuclear Reactor Regulation; U.S. Nuclear Regulatory Commission, Washington DC 20555–0001; telephone: 301–415–3229; email: Michael.Orenak@nrc.gov. I. Background Duke Energy Florida, Inc., is the holder of Facility License No. DPR–72. The license provides, among other things, that the facility is subject to all rules, regulations, and orders of the NRC now or hereafter in effect. The facility consists of a permanently shutdown and defueled pressurized water reactor located in Citrus County, Florida. By letter dated February 20, 2013 (ADAMS Accession No. ML13056A005), DEF submitted to the NRC the certification in accordance with §§ 50.82(a)(1)(i) and 50.82(a)(1)(ii) of Title 10 of the Code of Federal Regulations (10 CFR) indicating it permanently ceased power operations and that the CR3 reactor vessel was permanently defueled. II. Request/Action On July 17, 2013 (ADAMS Accession No. ML13204A397), the licensee requested an exemption from §§ 73.55(p)(1)(i) and 73.55(p)(1)(ii), pursuant to § 73.5, ‘‘Specific exemptions,’’ which requires, in part, that a licensed senior operator approves the suspension of security measures during certain emergency conditions or during severe weather. Portions of the letter dated July 17, 2013, contain sensitive unclassified nonsafeguards information (security-related) and, accordingly, have been withheld from public disclosure. The regulations in §§ 73.55(p)(1)(i) and 73.55(p)(1)(ii), respectively, specify that the suspension of security measures must be approved by, as a minimum, a licensed senior operator, or a licensed senior operator with input from the security supervisor or manager. The exemption request relates solely to the licensing requirements specified in the regulations for the staff directing suspension of security measures in E:\FR\FM\18DEN1.SGM 18DEN1

Agencies

[Federal Register Volume 79, Number 243 (Thursday, December 18, 2014)]
[Notices]
[Page 75595]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-29194]


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NUCLEAR REGULATORY COMMISSION


Advisory Committee on Reactor Safeguards Renewal

AGENCY: U.S. Nuclear Regulatory Commission.

ACTION: Notice of renewal of the Charter of the Advisory Committee on 
Reactor Safeguards (ACRS).

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SUMMARY: The Nuclear Regulatory Commission has determined that renewal 
of the charter for the ACRS until December 4, 2016, is in the public 
interest in connection with the statutory responsibilities assigned to 
the ACRS. This action is being taken in accordance with the Federal 
Advisory Committee Act.

FOR FURTHER INFORMATION CONTACT: Andrew L. Bates, Office of the 
Secretary, NRC, Washington, DC 20555; by telephone: (301) 415-1963, or 
email at ALB@NRC.GOV.

SUPPLEMENTARY INFORMATION: The Advisory Committee on Reactor Safeguards 
was established by Section 29 of the Atomic Energy Act (AEA) of 1954, 
as amended. Its purpose is to provide advice to the Commission with 
regard to the hazards of proposed or existing reactor facilities, to 
review each application for a construction permit or operating license 
for certain facilities specified in the AEA, and such other duties as 
the Commission may request. The AEA as amended by PL 100-456 also 
specifies that the Defense Nuclear Safety Board may obtain the advice 
and recommendations of the ACRS.
    Membership on the Committee includes individuals experienced in 
reactor operations, management; probabilistic risk assessment; analysis 
of reactor accident phenomena; design of nuclear power plant 
structures, systems and components; materials science; and mechanical, 
civil, and electrical engineering.

    Dated: December 8, 2014.
Andrew L. Bates,
Advisory Committee Management Officer.
[FR Doc. 2014-29194 Filed 12-17-14; 8:45 a.m.]
BILLING CODE 7590-01-P