Northern States Power Company: Prairie Island Independent Spent Fuel Storage Installation, 15158-15159 [2014-05938]

Download as PDF 15158 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852. FOR FURTHER INFORMATION CONTACT: Denise McGovern, Office of New Reactors, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001; telephone: 301–415–0681, email: Denise.McGovern@nrc.gov. SUPPLEMENTARY INFORMATION: Licensee Notification of Completion of ITAAC On January 17, 2014, South Carolina Electric and Gas, Inc. (the licensee) submitted an ITAAC closure notification (ICN) under § 52.99(c)(1) of Title 10 of the Code of Federal Regulations (10 CFR) informing the NRC that the licensee has successfully performed the required inspections, tests, and analyses for ITAAC 3.3.00.09, and that the specified acceptance criteria are met for Virgil C. Summer Nuclear Station Unit 2 (ADAMS Accession No. ML14023A676). This ITAAC was approved as part of the issuance of the combined license, NPF– 93, for this facility. emcdonald on DSK67QTVN1PROD with NOTICES NRC Staff Determination of Completion of ITAAC The NRC staff has determined that the inspections, tests, and analyses have been successfully completed, and that the specified acceptance criteria are met for Virgil C. Summer Nuclear Station Unit 2, ITAAC 3.3.00.09. This notice fulfills the staff’s obligations under 10 CFR 52.99(e)(1) to publish a notice in the Federal Register of the NRC staff’s determination of the successful completion of inspections, tests and analyses. The documentation of the NRC staff’s determination is in the ITAAC Closure Verification Evaluation Form (VEF), dated January 31, 2014 (ADAMS Accession No. ML14028A247). The VEF is a form that represents the NRC staff’s structured process for reviewing ICNs. The ICN presents a narrative description of how the ITAAC was completed, and the NRC’s ICN review process involves a determination on whether, among other things, (1) the ICN provides sufficient information, including a summary of the methodology used to perform the ITAAC, to demonstrate that the inspections, tests, and analyses have been successfully completed; (2) the ICN provides sufficient information to demonstrate that the acceptance criteria are met; and (3) any inspections for the ITAAC have been completed and any ITAAC findings associated with the ITAAC have been closed. The NRC staff’s determination of the successful completion of this ITAAC is VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 based on information available at this time and is subject to the licensee’s ability to maintain the condition that the acceptance criteria are met. If new information disputes the NRC staff’s determination, this ITAAC will be reopened as necessary. The NRC staff’s determination will be used to support a subsequent finding, pursuant to 10 CFR 52.103(g), at the end of construction that all acceptance criteria in the combined license are met. The ITAAC closure process is not finalized for this ITAAC until the NRC makes an affirmative finding under 10 CFR 52.103(g). Any future updates to the status of this ITAAC will be reflected on the NRC’s Web site at http://www.nrc.gov/reactors/ new-reactors/oversight/itaac.html. Dated at Rockville, Maryland, this 11th day of March 2014. For the Nuclear Regulatory Commission. Denise McGovern, Senior Project Manager, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. 2014–05936 Filed 3–17–14; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 72–10; NRC–2013–0207] Northern States Power Company: Prairie Island Independent Spent Fuel Storage Installation Nuclear Regulatory Commission. ACTION: License amendment application; issuance. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) reviewed an application by Northern States Power Company (NSPM) for amendment of Materials License No. SNM–2506 which authorizes NSPM to receive, possess, store, and transfer spent nuclear fuel and associated radioactive materials. The amendment sought to lower the allowed thermal conductance values for storage basket components utilized at the Prairie Island (PI) Independent Spent Fuel Storage Installation (ISFSI). ADDRESSES: Please refer to Docket ID NRC–2013–0207 when contacting the NRC about the availability of information regarding this document. You may access publicly-available information related to this action by the following methods: • Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC–2013–0207. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; email: Carol.Gallagher@nrc.gov. For SUMMARY: PO 00000 Frm 00064 Fmt 4703 Sfmt 4703 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 NRC Library at http://www.nrc.gov/readingrm/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 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. The Prairie Island License Amendment Request No. 8 package is available electronically in ADAMS under Accession No. ML13205A141. • 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: Chris Allen, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001; telephone: 301–287– 9225; email: William.Allen@nrc.gov. SUPPLEMENTARY INFORMATION: By application dated July 17, 2013, as supplemented December 5, 2013, NSPM submitted to the NRC, in accordance with Part 72 of Title 10 of the Code of Federal Regulations (10 CFR), a request to amend Special Nuclear Materials License No. SNM–2506 for its PI ISFSI site located in Welch, Minnesota. License No. SNM–2506 authorizes NSPM to receive, possess, store, and transfer spent nuclear fuel and associated radioactive materials resulting from the operation of the PI Power Plant in an ISFSI at the power plant site for a term of 20 years. Specifically, the amendment proposed lowering the allowed thermal conductance values for components used to fabricate storage baskets utilized at the PI ISFSI. The NRC issued a letter dated August 9, 2013, notifying NSPM that the application was acceptable for review. In accordance with 10 CFR 72.16, a Notice of Docketing was published in the Federal Register on September 16, 2013 (78 FR 56947). The Notice of Docketing included an opportunity to request a hearing and to petition for leave to intervene. No requests for a E:\FR\FM\18MRN1.SGM 18MRN1 Federal Register / Vol. 79, No. 52 / Tuesday, March 18, 2014 / Notices emcdonald on DSK67QTVN1PROD with NOTICES hearing or leave to intervene were submitted. The NRC prepared a safety evaluation report (SER) to document its review and evaluation of the amendment request. In addition, the NRC evaluated an assertion by PI that the amendment request satisfied the categorical exclusion criteria specified in 10 CFR 51.22(c)(11). Under 10 CFR 51.22(c)(11), a categorical exclusion is allowed for amendments to materials licenses which involve changes to process operations or equipment provided that (i) there is no significant change in the types or significant increase in the amounts of any effluents that may be released offsite, (ii) there is no significant increase in individual or cumulative occupational radiation exposure, (iii) there is no significant construction impact, and (iv) there is no significant increase in the potential for or consequences from radiological accidents. As explained in the SER, the NRC determined that the license amendment satisfied the 10 CFR 51.22(c)(11) categorical exclusion criteria. Consequently, an Environmental Assessment and Finding of No Significant Impact are not required. Upon completing its review, the staff determined the request complies with the standards and requirements of the Atomic Energy Act of 1954, as amended (the Act), as well as the NRC’s rules and regulations. As required by the Act and the NRC’s rules and regulations in 10 CFR Chapter I, the staff made the appropriate findings which are contained in the SER (ADAMS Accession No. ML14030A361). The NRC approved and issued Amendment No. 8 to Special Nuclear Materials License No. SNM–2506, held by NSPM for the receipt, possession, transfer, and storage of spent fuel and associated radioactive materials at the PI ISFSI. Pursuant to 10 CFR 72.46(d), the NRC is providing notice of the action taken. Amendment No. 8 was effective as of the date of issuance, March 10, 2014. Dated at Rockville, Maryland, this 10th day of March 2014. For the Nuclear Regulatory Commission. Michele Sampson, Chief, Licensing Branch, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards. [FR Doc. 2014–05938 Filed 3–17–14; 8:45 am] BILLING CODE 7590–01–P VerDate Mar<15>2010 18:34 Mar 17, 2014 Jkt 232001 NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–528, 50–529, 50–530; NRC– 2014–0053] Palo Verde Nuclear Generating Station Nuclear Regulatory Commission. ACTION: License amendment application; withdrawal by applicant. AGENCY: The U.S. Nuclear Regulatory Commission (NRC) has granted the request of Arizona Public Service Company (the licensee) to withdraw its application dated March 8, 2012, for a proposed amendment to Facility Operating License Nos. NPF–41, NPF– 51, and NPF–74. The proposed amendment would have revised the Technical Specifications (TS) to eliminate the use of the term CORE ALTERATIONS throughout the TS. ADDRESSES: Please refer to Docket ID NRC–2014–0053 when contacting the NRC about the availability of information regarding this document. You may access 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–2014–0053. Address questions about NRC dockets to Carol Gallagher; telephone: 301–287–3422; email: Carol.Gallagher@nrc.gov. For technical questions, contact the individual(s) listed in the FOR FURTHER INFORMATION CONTACT section of this document. • NRC’s Agencywide Documents Access and Management System (ADAMS): You may obtain 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 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: Jennivine Rankin, Office of Nuclear Reactor Regulation, telephone: 301– SUMMARY: PO 00000 Frm 00065 Fmt 4703 Sfmt 4703 15159 415–1530, email: Jennivine.Rankin@ nrc.gov; U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. SUPPLEMENTARY INFORMATION: The NRC has granted the request of Arizona Public Service Company (the licensee) to withdraw its March 8, 2012, application (ADAMS Accession No. ML12076A045), for proposed amendment to Facility Operating License Nos. NPF–41, NPF–51, and NPF–74, for the Palo Verde Nuclear Generating Station, Units 1, 2, and 3, respectively, located in Maricopa County, Arizona. The proposed amendment would have revised the Technical Specifications (TS) to eliminate the use of the term CORE ALTERATIONS throughout the TS. The proposed amendment incorporated changes reflected in Technical Specification Task Force (TSTF) Traveler 471–A, Revision 1, ‘‘Eliminate use of term CORE ALTERATIONS in ACTIONS and Notes.’’ The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on June 12, 2012 (77 FR 35071). The licensee supplemented their original application by letters dated October 11, 2012; January 31, 2013; and July 25, 2013; respectively (ADAMS Accession Nos. ML12286A330, ML13039A013, and ML13210A238). However, by letter dated February 13, 2014 (ADAMS Accession No. ML14051A103), the licensee withdrew the proposed change. Dated at Rockville, Maryland, this 7th day of March 2014. For the Nuclear Regulatory Commission. Balwant K. Singal, Senior Project Manager, Plant Licensing Branch IV–1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. 2014–05935 Filed 3–17–14; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 03029462; NRC–2014–0047] Request for Alternate Decommissioning Schedule: Department of the Navy Space and Naval Warfare Centers Pacific Nuclear Regulatory Commission. ACTION: License amendment application; opportunity to comment, request a hearing and petition for leave to intervene. AGENCY: E:\FR\FM\18MRN1.SGM 18MRN1

Agencies

[Federal Register Volume 79, Number 52 (Tuesday, March 18, 2014)]
[Notices]
[Pages 15158-15159]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: 2014-05938]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 72-10; NRC-2013-0207]


Northern States Power Company: Prairie Island Independent Spent 
Fuel Storage Installation

AGENCY: Nuclear Regulatory Commission.

ACTION: License amendment application; issuance.

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SUMMARY: The U.S. Nuclear Regulatory Commission (NRC) reviewed an 
application by Northern States Power Company (NSPM) for amendment of 
Materials License No. SNM-2506 which authorizes NSPM to receive, 
possess, store, and transfer spent nuclear fuel and associated 
radioactive materials. The amendment sought to lower the allowed 
thermal conductance values for storage basket components utilized at 
the Prairie Island (PI) Independent Spent Fuel Storage Installation 
(ISFSI).

ADDRESSES: Please refer to Docket ID NRC-2013-0207 when contacting the 
NRC about the availability of information regarding this document. You 
may access publicly-available information related to this action by the 
following methods:
     Federal Rulemaking Web site: Go to http://www.regulations.gov and search for Docket ID NRC-2013-0207. 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 NRC 
Library 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 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. The Prairie Island License Amendment Request No. 8 package 
is available electronically in ADAMS under Accession No. ML13205A141.
     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: Chris Allen, Office of Nuclear 
Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, 
Washington, DC 20555-0001; telephone: 301-287-9225; email: 
William.Allen@nrc.gov.

SUPPLEMENTARY INFORMATION: By application dated July 17, 2013, as 
supplemented December 5, 2013, NSPM submitted to the NRC, in accordance 
with Part 72 of Title 10 of the Code of Federal Regulations (10 CFR), a 
request to amend Special Nuclear Materials License No. SNM-2506 for its 
PI ISFSI site located in Welch, Minnesota. License No. SNM-2506 
authorizes NSPM to receive, possess, store, and transfer spent nuclear 
fuel and associated radioactive materials resulting from the operation 
of the PI Power Plant in an ISFSI at the power plant site for a term of 
20 years. Specifically, the amendment proposed lowering the allowed 
thermal conductance values for components used to fabricate storage 
baskets utilized at the PI ISFSI.
    The NRC issued a letter dated August 9, 2013, notifying NSPM that 
the application was acceptable for review. In accordance with 10 CFR 
72.16, a Notice of Docketing was published in the Federal Register on 
September 16, 2013 (78 FR 56947). The Notice of Docketing included an 
opportunity to request a hearing and to petition for leave to 
intervene. No requests for a

[[Page 15159]]

hearing or leave to intervene were submitted.
    The NRC prepared a safety evaluation report (SER) to document its 
review and evaluation of the amendment request. In addition, the NRC 
evaluated an assertion by PI that the amendment request satisfied the 
categorical exclusion criteria specified in 10 CFR 51.22(c)(11). Under 
10 CFR 51.22(c)(11), a categorical exclusion is allowed for amendments 
to materials licenses which involve changes to process operations or 
equipment provided that (i) there is no significant change in the types 
or significant increase in the amounts of any effluents that may be 
released offsite, (ii) there is no significant increase in individual 
or cumulative occupational radiation exposure, (iii) there is no 
significant construction impact, and (iv) there is no significant 
increase in the potential for or consequences from radiological 
accidents. As explained in the SER, the NRC determined that the license 
amendment satisfied the 10 CFR 51.22(c)(11) categorical exclusion 
criteria. Consequently, an Environmental Assessment and Finding of No 
Significant Impact are not required.
    Upon completing its review, the staff determined the request 
complies with the standards and requirements of the Atomic Energy Act 
of 1954, as amended (the Act), as well as the NRC's rules and 
regulations. As required by the Act and the NRC's rules and regulations 
in 10 CFR Chapter I, the staff made the appropriate findings which are 
contained in the SER (ADAMS Accession No. ML14030A361). The NRC 
approved and issued Amendment No. 8 to Special Nuclear Materials 
License No. SNM-2506, held by NSPM for the receipt, possession, 
transfer, and storage of spent fuel and associated radioactive 
materials at the PI ISFSI. Pursuant to 10 CFR 72.46(d), the NRC is 
providing notice of the action taken. Amendment No. 8 was effective as 
of the date of issuance, March 10, 2014.

    Dated at Rockville, Maryland, this 10th day of March 2014.

    For the Nuclear Regulatory Commission.
Michele Sampson,
Chief, Licensing Branch, Division of Spent Fuel Storage and 
Transportation, Office of Nuclear Material Safety and Safeguards.
[FR Doc. 2014-05938 Filed 3-17-14; 8:45 am]
BILLING CODE 7590-01-P