Entergy Operations, Inc.; Notice of Receipt and Availability of Application for a Combined License, 14849-14850 [E8-5522]

Download as PDF Federal Register / Vol. 73, No. 54 / Wednesday, March 19, 2008 / Notices Pike, Room O–1 F21, Rockville, MD 20852. OMB clearance requests are available at the NRC worldwide Web site: https://www.nrc.gov/public-involve/ doc-comment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions about the information collection requirements may be directed to the NRC Clearance Officer, Margaret A. Janney (T–5 F52), U.S. Nuclear Regulatory Commission, Washington, DC 20555–0001, by telephone at 301–415–7245, or by e-mail to INFOCOLLECTS@NRC.GOV. Dated at Rockville, Maryland, this 12th day of March 2008. For the Nuclear Regulatory Commission. Gregory Trussell, Acting NRC Clearance Officer, Office of Information Services. [FR Doc. E8–5517 Filed 3–18–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Agency Information Collection Activities: Proposed Collection; Comment Request U.S. Nuclear Regulatory Commission (NRC). ACTION: Notice of the OMB review of information collection and solicitation of public comment. jlentini on PROD1PC65 with NOTICES AGENCY: SUMMARY: The NRC has recently submitted to OMB for review the following proposal for the collection of information under the provisions of the Paperwork Reduction Act of 1995 (44 U.S.C. Chapter 35). The NRC hereby informs potential respondents that an agency may not conduct or sponsor, and that a person is not required to respond to, a collection of information unless it displays a currently valid OMB control number. The NRC published a Federal Register Notice with a 60-day comment period on this information collection on January 2, 2008. 1. Type of submission, new, revision, or extension: Revision. 2. The title of the information collection: 10 CFR Part 73—‘‘Physical Protection of Plants and Materials.’’ 3. Current OMB approval number: 3150–0002. 4. The form number if applicable: Not applicable. 5. How often the collection is required: On occasion, with the exception of the initial submittal of revised Security Plans, Safeguards Contingency Plans, and Security Training and Qualification Plans. VerDate Aug<31>2005 16:50 Mar 18, 2008 Jkt 214001 Required reports are submitted and evaluated as events occur. 6. Who will be required or asked to report: Nuclear power reactor licensees, licensed under 10 CFR Part 50 or 52 who possess, use, import, export, transport, or deliver to a carrier for transport, special nuclear material; Category I fuel facilities; Category II and III facilities; research and test reactors; and 262 other nuclear materials licensees. 7. An estimate of the number of annual responses: 86,264 (85,880 plus 384 recordkeepers). 8. The estimated number of annual respondents: 384. 9. An estimate of the total number of hours needed annually to complete the requirement or request: 578,863 hours (85,441 reporting [approximately 1 hour per response] and 493,422 recordkeeping [1,285 hours per recordkeeper]). 10. Abstract: NRC regulations in 10 CFR Part 73 prescribe requirements to establish and maintain a physical protection system and security organization with capabilities for protection of: (1) Special nuclear material (SNM) at fixed sites, (2) SNM in transit, and (3) plants in which SNM is used. The objective is to ensure that activities involving special nuclear material are consistent with interests of common defense and security and that these activities do not constitute an unreasonable risk to public health and safety. The information in the reports and records submitted by licensees is used by the NRC staff to ensure that the health and safety of the public and the environment are protected, and licensee possession and use of special nuclear material is in compliance with license and regulatory requirements. A copy of the final supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O–1 F21, Rockville, MD 20852. OMB clearance requests are available at the NRC worldwide Web site: https://www.nrc.gov/public-involve/ doc-comment/omb/. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions should be directed to the OMB reviewer listed below by April 18, 2008. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. Nathan J. Frey, Office of Information and Regulatory Affairs (3150–0002), NEOB–10202, Office of Management PO 00000 Frm 00081 Fmt 4703 Sfmt 4703 14849 and Budget, Washington, DC 20503. Comments can also be e-mailed to Nathan_J._Frey@omb.eop.gov or submitted by telephone at (202) 395– 7345. The NRC Clearance Officer is Margaret A. Janney, (301) 415–7245. Dated at Rockville, Maryland, this 12th day of March, 2008. For the Nuclear Regulatory Commission. Gregory Trussell, Acting NRC Clearance Officer, Office of Information Services. [FR Doc. E8–5518 Filed 3–18–08; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Entergy Operations, Inc.; Notice of Receipt and Availability of Application for a Combined License On February 27, 2008, Entergy Operations, Inc. (EOI), on behalf of itself and Entergy Mississippi, Inc., Entergy Louisiana, LLC, Entergy Gulf States Louisiana, LLC, and System Energy Resources, Inc., filed with the U. S. Nuclear Regulatory Commission (NRC, the Commission) pursuant to Section 103 of the Atomic Energy Act and Title 10 of the Code of Federal Regulations (10 CFR) Part 52, ‘‘Licenses, Certifications, and Approvals for Nuclear Power Plants,’’ an application for a combined license (COL) for an economic simplified boiling water reactor (ESBWR) nuclear power plant at the Grand Gulf Nuclear Station (GGNS) site located in Claiborne County, Mississippi. The reactor is to be identified as GGNS Unit 3. An applicant may seek a COL in accordance with Subpart C of 10 CFR Part 52. The information submitted by the applicant includes certain administrative information such as financial qualifications submitted pursuant to 10 CFR 52.77, as well as technical information submitted pursuant to 10 CFR 52.79. Subsequent Federal Register notices will address the acceptability of the tendered COL application for docketing and provisions for participation of the public in the COL review process. A copy of the application is available for public inspection at the Commission’s Public Document Room (PDR), located at One White Flint North, Public File Area O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland, and via the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, https://www.nrc.gov/ E:\FR\FM\19MRN1.SGM 19MRN1 14850 Federal Register / Vol. 73, No. 54 / Wednesday, March 19, 2008 / Notices reading-rm/adams.html. The accession number for the application is ML080640433. Future publicly available documents related to the application will also be posted in ADAMS. Persons who do not have access to ADAMS, or who encounter problems in accessing the documents located in ADAMS, should contact the NRC Public Document Room staff by telephone at 1– 800–397–4209 or 301–415–4737, or by e-mail to pdr@nrc.gov. The application is also available at https://www.nrc.gov/ reactors/new-licensing/col.html. operation of the facility in accordance with the proposed amendment would not: (1) Involve a significant increase in the probability or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accident previously evaluated; or (3) involve a significant reduction in a margin of safety. As required by 10 CFR 50.91(a), the licensee has provided its analysis of the issue of no significant hazards consideration, which is presented below: Dated at Rockville, Maryland, this 10th day of March, 2008. For the Nuclear Regulatory Commission. Eric R. Oesterle, Senior Project Manager, ESBWR/ABWR Projects Branch 1, Division of New Reactor Licensing, Office of New Reactors. [FR Doc. E8–5522 Filed 3–18–08; 8:45 am] 1. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? The probability or consequences of accidents previously evaluated in the [Updated Final Safety Analysis Report] are unaffected by this proposed change. The duration for obtaining neutron detector plateau curves is not an initiator of any accident previously analyzed. There is no change to any equipment response or accident scenario, and this change results in no additional challenges to fission product barrier integrity. The proposed change does not alter the design, configuration, operation, or function of any plant system, structure, or component. The requested amendment modifies the frequency of the channel calibrations for the intermediate and power range detectors by permitting 24 hours to perform the SR [surveillance requirement] (measure and obtain neutron detector plateau curves) after achieving steady-state operation at rated thermal power. This change has no impact on the consequences or probability of any accident previously evaluated. The proposed change does not impact the ability of the nuclear instrumentation, reactor protection system, or any other system, structure, or component to perform its intended function to mitigate the consequences of an accident within acceptable limits. The proposed change does not affect the source term, containment isolation, or radiological assumptions used in analyzing the consequences of accidents previously evaluated. Further, the proposed change neither increases the type or amount of radioactivity released offsite nor increases public or occupational radiation exposures. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? No new accident scenarios, failure mechanisms, or limiting single failures are introduced as a result of the proposed change. The proposed change does not challenge the performance or integrity of any safety-related system. The proposed change neither installs nor removes any plant equipment, and it does not alter the design, physical configuration, or operation of any plant structure, system, or component. No BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket No. 50–443] jlentini on PROD1PC65 with NOTICES Seabrook Station, Unit No. 1; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards; Consideration Determination and Opportunity for a Hearing The U.S. Nuclear Regulatory Commission (the Commission or NRC) is considering issuance of an amendment to Facility Operating License No. NPF–86 issued to FPL Energy Seabrook, LLC (the licensee) for operation of Seabrook Station, Unit No. 1, located in Rockingham County, New Hampshire. The proposed amendment would revise Technical Specification (TS) Table 4.3–1, ‘‘Reactor Trip System Instrumentation Surveillance Requirements’’ to require the initial plateau curves to be measured within 24 hours after attaining 100 percent steadystate power. Currently, initial plateau curves are required to be taken within 24 hours of entry into Mode 2. Before issuance of the proposed license amendment, the Commission will have made findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission’s regulations. The Commission has made a proposed determination that the amendment request involves no significant hazards consideration. Under the Commission’s regulations in Title 10 of the Code of Federal Regulations (10 CFR), Section 50.92, this means that VerDate Aug<31>2005 16:50 Mar 18, 2008 Jkt 214001 PO 00000 Frm 00082 Fmt 4703 Sfmt 4703 physical changes are being made to the plant, so no new accident causal mechanisms are being introduced. Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? The margin of safety associated with the acceptance criteria of any accident is unchanged. The proposed change will have no affect on the operability or performance of the safety-related systems and components. The proposed change does not alter the design, configuration, operation, or function of any plant system, structure, or component. The ability of any operable structure, system, or component to perform its designated safety function is unaffected by this change. With this change, the TS will continue to require operable nuclear instrumentation. The proposed change does not create an initiating event, increase the likelihood of an initiating event, affect the ability to mitigate an event, affect containment performance, or affect operator actions in response to an event. Therefore, the margin of safety as defined in the TS is not reduced and the proposed change does not involve a significant reduction in a margin of safety. The NRC staff has reviewed the licensee’s analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. The Commission is seeking public comments on this proposed determination. Any comments received within 30 days after the date of publication of this notice will be considered in making any final determination. Normally, the Commission will not issue the amendment until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendment before expiration of the 60day period provided that its final determination is that the amendment involves no significant hazards consideration. In addition, the Commission may issue the amendment prior to the expiration of the 30-day comment period should circumstances change during the 30-day comment period such that failure to act in a timely way would result, for example, in derating or shutdown of the facility. Should the Commission take action prior to the expiration of either the comment period or the notice period, it will publish in the Federal Register a notice of issuance. Should the Commission make a final No Significant Hazards Consideration Determination, any hearing will take place after issuance. The Commission expects that E:\FR\FM\19MRN1.SGM 19MRN1

Agencies

[Federal Register Volume 73, Number 54 (Wednesday, March 19, 2008)]
[Notices]
[Pages 14849-14850]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E8-5522]


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NUCLEAR REGULATORY COMMISSION


Entergy Operations, Inc.; Notice of Receipt and Availability of 
Application for a Combined License

    On February 27, 2008, Entergy Operations, Inc. (EOI), on behalf of 
itself and Entergy Mississippi, Inc., Entergy Louisiana, LLC, Entergy 
Gulf States Louisiana, LLC, and System Energy Resources, Inc., filed 
with the U. S. Nuclear Regulatory Commission (NRC, the Commission) 
pursuant to Section 103 of the Atomic Energy Act and Title 10 of the 
Code of Federal Regulations (10 CFR) Part 52, ``Licenses, 
Certifications, and Approvals for Nuclear Power Plants,'' an 
application for a combined license (COL) for an economic simplified 
boiling water reactor (ESBWR) nuclear power plant at the Grand Gulf 
Nuclear Station (GGNS) site located in Claiborne County, Mississippi. 
The reactor is to be identified as GGNS Unit 3.
    An applicant may seek a COL in accordance with Subpart C of 10 CFR 
Part 52. The information submitted by the applicant includes certain 
administrative information such as financial qualifications submitted 
pursuant to 10 CFR 52.77, as well as technical information submitted 
pursuant to 10 CFR 52.79.
    Subsequent Federal Register notices will address the acceptability 
of the tendered COL application for docketing and provisions for 
participation of the public in the COL review process.
    A copy of the application is available for public inspection at the 
Commission's Public Document Room (PDR), located at One White Flint 
North, Public File Area O1 F21, 11555 Rockville Pike (first floor), 
Rockville, Maryland, and via the Agencywide Documents Access and 
Management System (ADAMS) Public Electronic Reading Room on the 
Internet at the NRC Web site, https://www.nrc.gov/

[[Page 14850]]

reading-rm/adams.html. The accession number for the application is 
ML080640433. Future publicly available documents related to the 
application will also be posted in ADAMS. Persons who do not have 
access to ADAMS, or who encounter problems in accessing the documents 
located in ADAMS, should contact the NRC Public Document Room staff by 
telephone at 1-800-397-4209 or 301-415-4737, or by e-mail to 
pdr@nrc.gov. The application is also available at https://www.nrc.gov/
reactors/new-licensing/col.html.

    Dated at Rockville, Maryland, this 10th day of March, 2008.

    For the Nuclear Regulatory Commission.
Eric R. Oesterle,
Senior Project Manager, ESBWR/ABWR Projects Branch 1, Division of New 
Reactor Licensing, Office of New Reactors.
 [FR Doc. E8-5522 Filed 3-18-08; 8:45 am]
BILLING CODE 7590-01-P
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