Notice of Issuance of Environmental Assessment and Finding of No Significant Impact; Entergy Operations, Inc., Grand Gulf Nuclear Station, Independent Spent Fuel Storage Installation, 28071-28072 [E9-13711]

Download as PDF Federal Register / Vol. 74, No. 112 / Friday, June 12, 2009 / Notices NATIONAL SCIENCE FOUNDATION Committee on Equal Opportunities in Science and Engineering (CEOSE); Notice of Meeting In accordance with the Federal Advisory Committee Act (Pub. L. 92– 463, as amended), the National Science Foundation announces the following meeting: Name: Committee on Equal Opportunities in Science and Engineering (1173). Dates/Time: June 29, 2009, 8:30 a.m.–5:30 p.m. June 30, 2009, 8:30 a.m.–2 p.m. Place: National Science Foundation (NSF), 4201 Wilson Boulevard, Room 1235 Arlington, VA 22230. To help facilitate your access into the building, please contact the individual listed below prior to the meeting so that a visitors badge may be prepared for you in advance. Type of Meeting: Open. Contact Person: Dr. Margaret E.M. Tolbert, Senior Advisor and CEOSE Executive Liaison, Office of Integrative Activities, National Science Foundation, 4201 Wilson Boulevard, Arlington, VA 22230. Telephone Numbers: (703) 292–4216, (703) 292–8040, mtolbert@nsf.gov. Minutes: Minutes may be obtained from the Executive Liaison at the above address or the Web site at https://www.nsf.gov/od/oia/ activities/ceose/index.jsp. Purpose of Meeting: To study NSF programs and policies and provide advice and recommendations concerning broadening participation in science and engineering. Agenda Monday, June 29, 2009 Opening Statement by the CEOSE Chair. Presentations and Discussions: ✓ The Intersection of Science and Engineering with Diversity and Inclusion; ✓ Women and Underrepresented Minorities in STEM: a Science Policy Perspective; ✓ A Conversation with the Deputy Director of the National Science Foundation; ✓ Plans for the CEOSE Mini-Symposium on Women of Color in Science and Engineering; ✓ Key Points from the ‘‘Understanding Interventions that Broaden Participation in Research Careers Conference’’; ✓ Race, Gender, Ethnicity, and Disability in China—A CEOSE Member’s Perspective; ✓ The 2007–2008 CEOSE Biennial Report to Congress; ✓ Concurrent Meetings of CEOSE Ad Hoc Subcommittees; ✓ Reports by Ad Hoc Subcommittee Chairs. Tuesday, June 30, 2009 Opening Statement by the CEOSE Chair. Presentations and Discussions: ✓ NSF Program Management Curriculum, Program Directors’ Seminar With a Focus on Broadening Participation Aspects; VerDate Nov<24>2008 17:53 Jun 11, 2009 Jkt 217001 ✓ Broadening Participation at the National Science Foundation and the Impact of the American Recovery and Reinvestment Act and America Competes Act; ✓ Reports by CEOSE Liaisons to Various NSF Advisory Committees; ✓ Completion of Unfinished Business. Dated: June 9, 2009. Susanne Bolton, Committee Management Officer. [FR Doc. E9–13842 Filed 6–11–09; 8:45 am] BILLING CODE 7555–01–P NUCLEAR REGULATORY COMMISSION [Dockets 50–0416 and 72–0050; NRC–2009– 0230] Notice of Issuance of Environmental Assessment and Finding of No Significant Impact; Entergy Operations, Inc., Grand Gulf Nuclear Station, Independent Spent Fuel Storage Installation AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact. FOR FURTHER INFORMATION CONTACT: John Goshen, Project Manager, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Telephone: (301) 492–3325; fax number: (301) 492–3342; e-mail: john.goshen@nrc.gov. SUPPLEMENTARY INFORMATION: I. Environmental Assessment (EA) Identification of Proposed Action: By letter dated December 22, 2008, as supplemented March 20, 2009, Entergy Operations, Inc. (Entergy) submitted to the United States Nuclear Regulatory Commission (NRC) a one-time exemption request from the requirements of 10 CFR 72.212(a)(2) and (b)(7) for four HI–STORM 100 System Model 68 Multi-Purpose Canisters (MPCs) at the Grand Gulf Nuclear Station (GGNS) Independent Spent Fuel Storage Facility (ISFSI) due to noncompliance with two of the terms and conditions of Certificate of Compliance (CoC)–1014, Amendment No. 2 at the time of cask loading. Section 72.212(a)(2) limits the general license issued by 10 CFR 72.210 to the storage of spent fuel in casks approved under the provisions of Part 72. Section 72.212(b)(7) requires that the general licensee to comply with the terms and conditions of the applicable CoC. PO 00000 Frm 00077 Fmt 4703 Sfmt 4703 28071 In December 2006, due to a database error, Entergy loaded four MPCs with individual fuel assemblies (IFAs) that exceeded the maximum burnup limits and maximum decay heat limits specified in the CoC–1014, Amendment No. 2, Appendix B, Section 2.1. Additionally, the supplemental cooling required by the CoC–1014, Amendment No. 2, Appendix A, Section 3.1.4 for the four MPCs had not been implemented. Entergy identified the non-compliances on June 18, 2008, in an event report to the NRC, along with a preliminary evaluation that determined that fuel cladding temperatures had not exceeded thermal limits during any time during the affected period. The proposed action before the NRC is whether to grant this exemption request pursuant to 10 CFR 72.7. Need for the Proposed Action: Entergy requested the exemption from 10 CFR 72.212(a)(2) and 10 CFR 72.212(b)(7) to allow continued, non-compliant storage of the IFAs in the affected MPCs. Environmental Impacts of the Proposed Action: The proposed action under consideration would allow Entergy a one-time exemption from 10 CFR 72.212(a)(2) and 10 CFR 72.212(b)(7) for the four affected MPCs at GGNS ISFSI. Entergy’s evaluation and a thermal analysis by Holtec, the fabricator of the cask system, determined that the fuel cladding was intact, and therefore, the integrity of the affected MPCs and the contained IFAs was not compromised. The heat loads in the affected casks have decreased to within the limits set by CoC–1014. The NRC staff concludes that the requested exemption has low safety significance and that, in accordance with 10 CFR 72.7, approval of the requested exemption will not endanger life or property or the common defense and security and is otherwise in the public interest. The NRC staff further concludes that approving the exemption request would have no significant impact on the environment. Alternative to the Proposed Action: The no-action alternative to the proposed action would be to deny approval of the exemption. Denial of the exemption request would require Entergy to unload the affected MPCs. Unloading the MPCs would expose Entergy’s personnel to additional radiation, generate contaminated waste, and run the risks of a possible fuel handling accident and a possible heavy load handling accident. Given the risks associated with unloading the casks and that there are no significant radiological or nonradiological environmental impacts arising from the continued storage of the E:\FR\FM\12JNN1.SGM 12JNN1 28072 Federal Register / Vol. 74, No. 112 / Friday, June 12, 2009 / Notices IFAs in the affected MPCs, the NRC concludes that the preferred alternative is to grant the exemption request. II. Finding of No Significant Impact The environmental impacts of the proposed action have been reviewed in accordance with the requirements set forth in 10 CFR Part 51. Based upon the foregoing Environmental Assessment, the Commission finds that the proposed action of granting an exemption from 10 CFR 72.212(a)(2) and 10 CFR 72.212(b)(7) will not significantly impact the quality of the human environment. Accordingly, the Commission has determined not to prepare an environmental impact statement for the proposed exemption. III. Further Information The document related to this action is available electronically at the NRC’s Electronic Reading Room at https:// www.nrc.gov/reading-rm/adams.html. A copy of the exemption request, dated December 22, 2008, can be found on this site using the Agencywide Document Access and Management System (ADAMS), accession number ML091470104. If you do not have access to ADAMS or if there are problems in accessing the document 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@nrc.gov. This document may also be viewed electronically on the public computers located at the NRC’s Public Document Room (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, MD, this 3rd day of June 2009. For the Nuclear Regulatory Commission. Eric Benner, Chief, Licensing Branch, Division of Spent Fuel Storage and Transportation, Office of Nuclear Material Safety and Safeguards. [FR Doc. E9–13711 Filed 6–11–09; 8:45 am] BILLING CODE 7590–01–P VerDate Nov<24>2008 17:53 Jun 11, 2009 Jkt 217001 NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–424 and 50–425; NRC– 2009–0237] Southern Nuclear Operating Co., Inc., Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia: City of Dalton, Georgia Vogtle Electric Generating Plant, Units 1 and 2; Notice of Issuance of Renewed Facility Operating License Nos. NPF–68 and NPF–81 for an Additional 20-Year Period Record of Decision Notice is hereby given that the U.S. Nuclear Regulatory Commission (NRC or the Commission) has issued Renewed Facility Operating License Nos. NPF–68 and NPF–81 to Southern Nuclear Operating Company, Inc. (licensee), Georgia Power Company, Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, co-owners of the Vogtle Electric Generating Plant (VEGP), Units 1 and 2. Renewed Facility Operating License Nos. NPF–68 and NPF–81 authorize operation of VEGP by the licensee at reactor core power levels not in excess of 3,625.6 megawatts thermal for each unit, in accordance with the provisions of the VEGP renewed licenses and their technical specifications. This notice also serves as the record of decision for the renewal of Facility Operating License Nos. NPF–68 and NPF–81 for VEGP, consistent with Title 10 of the Code of Federal Regulations (10 CFR) Section 51.103, ‘‘Record of Decision-General.’’ As discussed in the final supplemental environmental impact statement for VEGP (NUREG– 1437, ‘‘Generic Environmental Impact Statement for License Renewal of Nuclear Plants,’’ Supplement 34, ‘‘Vogtle Electric Generating Plant, Units 1 and 2,’’ issued December 2008), the Commission considered a range of reasonable alternatives that included power generation from coal, natural gas, oil, wind, solar, hydropower, geothermal, wood waste, municipal solid waste, and other biomass-derived fuels; delayed retirement; utilitysponsored conservation, and a combination of alternatives, including a no-action alternative. The factors considered in the record of decision appear in Supplement 34. VEGP is a dual-unit pressurized-water reactor designed by Westinghouse Electric Corporation that is located in Wayne County, GA. The site is located approximately 25 miles south of Augusta, GA. The application for the renewed licenses complied with the standards and requirements of the PO 00000 Frm 00078 Fmt 4703 Sfmt 4703 Atomic Energy Act of 1954, as amended (the Act), and the Commission’s regulations. As required by the Act and the Commission’s regulations in 10 CFR Chapter I, the Commission has made appropriate findings, which the license sets forth. Prior public notice of the action involving the proposed issuance of the renewed license and of an opportunity for a hearing regarding the proposed issuance of the renewed license was published in the Federal Register on August 21, 2007 (72 FR 46680). For further details with respect to this action, see (1) the Southern Nuclear Operating Company, Inc., Oglethorpe Power Corporation, Municipal Electric Authority of Georgia, and City of Dalton, Georgia, license renewal application for VEGP, Units 1 and 2, dated June 29, 2007, as supplemented by letters dated through February 16, 2009, (2) the Commission’s safety evaluation report (NUREG–1920, ‘‘Safety Evaluation Report Related to the License Renewal of the Vogtle Electric Generating Plant, Units 1 and 2,’’ Volumes 1 and 2, issued April 2009), (3) the licensee’s updated safety analysis report, and (4) the Commission’s final environmental impact statement (NUREG–1437, Supplement 34). These documents are available at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852, and can be viewed from the NRC Public Electronic Reading Room at https:// www.nrc.gov/reading-rm/adams.html. Copies of Renewed Facility Operating License Nos. NPF–68 and NPF–81 may be obtained by writing to the U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, Attention: Director, Division of License Renewal. Copies of the safety evaluation report for VEGP Units 1 and 2 (NUREG–1920, Volumes 1 and 2) and the final environmental impact statement (NUREG–1437, Supplement 34) may be purchased from the National Technical Information Service, U.S. Department of Commerce, Springfield, VA 22161–0002 (https://www.ntis.gov), 703–605–6000; or from the Superintendent of Documents, U.S. Government Printing Office, P.O. Box 371954, Pittsburgh, PA 15250–7954 (https://www.gpoaccess.gov), 202–512– 1800. All orders should clearly identify the NRC publication number and the requester’s Government Printing Office deposit account number or a VISA or MasterCard number and expiration date. Dated at Rockville, MD, this 3rd day of June 2009. E:\FR\FM\12JNN1.SGM 12JNN1

Agencies

[Federal Register Volume 74, Number 112 (Friday, June 12, 2009)]
[Notices]
[Pages 28071-28072]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E9-13711]


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NUCLEAR REGULATORY COMMISSION

[Dockets 50-0416 and 72-0050; NRC-2009-0230]


Notice of Issuance of Environmental Assessment and Finding of No 
Significant Impact; Entergy Operations, Inc., Grand Gulf Nuclear 
Station, Independent Spent Fuel Storage Installation

AGENCY: Nuclear Regulatory Commission.

ACTION: Issuance of Environmental Assessment and Finding of No 
Significant Impact.

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

FOR FURTHER INFORMATION CONTACT: John Goshen, Project Manager, Division 
of Spent Fuel Storage and Transportation, Office of Nuclear Material 
Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, 
DC 20555. Telephone: (301) 492-3325; fax number: (301) 492-3342; e-
mail: john.goshen@nrc.gov.

SUPPLEMENTARY INFORMATION: 

I. Environmental Assessment (EA)

    Identification of Proposed Action: By letter dated December 22, 
2008, as supplemented March 20, 2009, Entergy Operations, Inc. 
(Entergy) submitted to the United States Nuclear Regulatory Commission 
(NRC) a one-time exemption request from the requirements of 10 CFR 
72.212(a)(2) and (b)(7) for four HI-STORM 100 System Model 68 Multi-
Purpose Canisters (MPCs) at the Grand Gulf Nuclear Station (GGNS) 
Independent Spent Fuel Storage Facility (ISFSI) due to non-compliance 
with two of the terms and conditions of Certificate of Compliance 
(CoC)-1014, Amendment No. 2 at the time of cask loading. Section 
72.212(a)(2) limits the general license issued by 10 CFR 72.210 to the 
storage of spent fuel in casks approved under the provisions of Part 
72. Section 72.212(b)(7) requires that the general licensee to comply 
with the terms and conditions of the applicable CoC.
    In December 2006, due to a database error, Entergy loaded four MPCs 
with individual fuel assemblies (IFAs) that exceeded the maximum burnup 
limits and maximum decay heat limits specified in the CoC-1014, 
Amendment No. 2, Appendix B, Section 2.1. Additionally, the 
supplemental cooling required by the CoC-1014, Amendment No. 2, 
Appendix A, Section 3.1.4 for the four MPCs had not been implemented. 
Entergy identified the non-compliances on June 18, 2008, in an event 
report to the NRC, along with a preliminary evaluation that determined 
that fuel cladding temperatures had not exceeded thermal limits during 
any time during the affected period. The proposed action before the NRC 
is whether to grant this exemption request pursuant to 10 CFR 72.7.
    Need for the Proposed Action: Entergy requested the exemption from 
10 CFR 72.212(a)(2) and 10 CFR 72.212(b)(7) to allow continued, non-
compliant storage of the IFAs in the affected MPCs.
    Environmental Impacts of the Proposed Action: The proposed action 
under consideration would allow Entergy a one-time exemption from 10 
CFR 72.212(a)(2) and 10 CFR 72.212(b)(7) for the four affected MPCs at 
GGNS ISFSI. Entergy's evaluation and a thermal analysis by Holtec, the 
fabricator of the cask system, determined that the fuel cladding was 
intact, and therefore, the integrity of the affected MPCs and the 
contained IFAs was not compromised. The heat loads in the affected 
casks have decreased to within the limits set by CoC-1014.
    The NRC staff concludes that the requested exemption has low safety 
significance and that, in accordance with 10 CFR 72.7, approval of the 
requested exemption will not endanger life or property or the common 
defense and security and is otherwise in the public interest. The NRC 
staff further concludes that approving the exemption request would have 
no significant impact on the environment.
    Alternative to the Proposed Action: The no-action alternative to 
the proposed action would be to deny approval of the exemption. Denial 
of the exemption request would require Entergy to unload the affected 
MPCs. Unloading the MPCs would expose Entergy's personnel to additional 
radiation, generate contaminated waste, and run the risks of a possible 
fuel handling accident and a possible heavy load handling accident.
    Given the risks associated with unloading the casks and that there 
are no significant radiological or non-radiological environmental 
impacts arising from the continued storage of the

[[Page 28072]]

IFAs in the affected MPCs, the NRC concludes that the preferred 
alternative is to grant the exemption request.

II. Finding of No Significant Impact

    The environmental impacts of the proposed action have been reviewed 
in accordance with the requirements set forth in 10 CFR Part 51. Based 
upon the foregoing Environmental Assessment, the Commission finds that 
the proposed action of granting an exemption from 10 CFR 72.212(a)(2) 
and 10 CFR 72.212(b)(7) will not significantly impact the quality of 
the human environment. Accordingly, the Commission has determined not 
to prepare an environmental impact statement for the proposed 
exemption.

III. Further Information

    The document related to this action is available electronically at 
the NRC's Electronic Reading Room at https://www.nrc.gov/reading-rm/adams.html. A copy of the exemption request, dated December 22, 2008, 
can be found on this site using the Agencywide Document Access and 
Management System (ADAMS), accession number ML091470104. If you do not 
have access to ADAMS or if there are problems in accessing the document 
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@nrc.gov.
    This document may also be viewed electronically on the public 
computers located at the NRC's Public Document Room (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, MD, this 3rd day of June 2009.
    For the Nuclear Regulatory Commission.
Eric Benner,
Chief, Licensing Branch, Division of Spent Fuel Storage and 
Transportation, Office of Nuclear Material Safety and Safeguards.
[FR Doc. E9-13711 Filed 6-11-09; 8:45 am]
BILLING CODE 7590-01-P
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