Notices. NUCLEAR REGULATORY COMMISSION

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BILLING CODE 7555-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 50-271] Entergy Nuclear Operations, Inc., Vermont Yankee Nuclear Power Station; Notice of Acceptance for Docketing of the Application and Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License No. DPR-28 for an Additional 20-Year Period The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering an application for the renewal of Operating License No. DPR-28, which authorizes Entergy Nuclear Operations, Inc., to operate the Vermont Yankee Nuclear Power Station at 1912 megawatts

(MWt)thermal. The renewed license would authorize the applicant to operate the Vermont Yankee Nuclear Power Station for an additional 20 years beyond the period specified in the current license. The current operating license for the Vermont Yankee Nuclear Power Station expires on March 21, 2012. The Commission's staff received the application dated January 25, 2006, as supplemented by letter dated March 15, 2006, from Entergy Nuclear Operations, Inc., pursuant to 10 CFR Part 54, to renew the Operating License No. DPR-28 for Vermont Yankee Nuclear Power Station. A Notice of Receipt and Availability of the license renewal application, “Entergy Nuclear Operations, Inc. Notice of Receipt and Availability of Application for Renewal of Vermont Yankee Nuclear Power Station Facility Operating License No. DPR-28 for an Additional 20-Year Period,” was published in the **Federal Register** on February 6, 2006 (71 FR 6102). The Commission's staff has determined that Entergy Nuclear Operations, Inc. has submitted sufficient information in accordance with 10 CFR 54.19, 54.21, 54.22, 54.23, and 51.53(c), and the application is acceptable for docketing. The current Docket No. 50-271 for Operating License No. DPR-28 will be retained. The docketing of the renewal application does not preclude requesting additional information as the review proceeds, nor does it predict whether the Commission will grant or deny the application. Before issuance of each requested renewed license, the NRC will have made the findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. In accordance with 10 CFR 54.29, the NRC will issue a renewed license on the basis of its review if it finds that actions have been identified and have been or will be taken with respect to:

(1)Managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified as requiring aging management review, and

(2)time-limited aging analyses that have been identified as requiring review, such that there is reasonable assurance that the activities authorized by the renewed license will continue to be conducted in accordance with the current licensing basis (CLB), and that any changes made to the plant?s CLB comply with the Act and the Commission's regulations. Additionally, in accordance with 10 CFR 51.95(c), the NRC will prepare an environmental impact statement that is a supplement to the Commission's NUREG-1437, “Generic Environmental Impact Statement for License Renewal of Nuclear Power Plants,” dated May 1996. Pursuant to 10 CFR 51.26, and as part of the environmental scoping process, the staff intends to hold a public scoping meeting. Detailed information regarding this meeting will be the subject of a separate **Federal Register** notice. Within 60 days after the date of publication of this **Federal Register** Notice, the applicant may file a request for a hearing, and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene with respect to the renewal of the license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's “Rules of Practice for Domestic Licensing Proceedings” in 10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 2.309, which is available at the Commission's Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland 20852 and is accessible from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at *http://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's PDR reference staff by telephone at 1-800-397-4209, or by e-mail at *pdr@nrc.gov* . If a request for a hearing/petition for leave to intervene is filed within the 60-day period, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel will rule on the request/petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order. In the event that no request for a hearing/petition for leave to intervene is filed within the 60-day period, the NRC may, upon completion of its evaluations and upon making the findings required under 10 CFR Parts 51 and 54, renew the license without further notice. As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding, taking into consideration the limited scope of matters that may be considered pursuant to 10 CFR Parts 51 and 54. The petition must specifically explain the reasons why intervention should be permitted with particular reference to the following factors:

(1)The nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding;

(2)the nature and extent of the requestor's/petitioner's property, financial, or other interest in the proceeding; and

(3)the possible effect of any decision or order which may be entered in the proceeding on the requestor's/petitioner's interest. The petition must also set forth the specific contentions which the petitioner/requestor seeks to have litigated at the proceeding. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the requestor/petitioner shall provide a brief explanation of the bases of each contention and a concise statement of the alleged facts or the expert opinion that supports the contention on which the requestor/petitioner intends to rely in proving the contention at the hearing. The requestor/petitioner must also provide references to those specific sources and documents of which the requestor/petitioner is aware and on which the requestor/petitioner intends to rely to establish those facts or expert opinion. The requestor/petitioner must provide sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. 1 Contentions shall be limited to matters within the scope of the action under consideration. The contention must be one that, if proven, would entitle the requestor/petitioner to relief. A requestor/petitioner who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party. 1 To the extent that the application contains attachments and supporting documents that are not publicly available because they are asserted to contain safeguards or proprietary information, petitioners desiring access to this information should contact the applicant or applicant's counsel to discuss the need for a protective order. The Commission requests that each contention be given a separate numeric or alpha designation within one of the following groups:

(1)Technical (primarily related to safety concerns);

(2)environmental; or

(3)miscellaneous. As specified in 10 CFR 2.309, if two or more requestors/petitioners seek to co-sponsor a contention or propose substantially the same contention, the requestors/petitioners will be required to jointly designate a representative who shall have the authority to act for the requestors/petitioners with respect to that contention. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing. A request for a hearing or a petition for leave to intervene must be filed by:

(1)First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC, 20555-0001, Attention: Rulemaking and Adjudications Staff;

(2)courier, express mail, and expedited delivery services: Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland, 20852, Attention: Rulemaking and Adjudications Staff;

(3)e-mail addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, *HEARINGDOCKET@NRC.GOV* ; or

(4)facsimile transmission addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC, Attention: Rulemakings and Adjudications Staff at 301-415-1101, verification number is 301-415-1966. 2 A copy of the request for hearing and petition for leave to intervene must also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and it is requested that copies be transmitted either by means of facsimile transmission to 301-415-3725 or by e-mail to *OGCMailCenter@nrc.gov* . A copy of the request for hearing and petition for leave to intervene should also be sent to the attorney for the applicant, Mr. Terrence A. Burke, Entergy Nuclear, 1340 Echelon Parkway, mail stop M-ECN-62, Jackson, MS 39213. 2 If the request/petition is filed by e-mail or facsimile, an original and two copies of the document must be mailed within 2

(two)business days thereafter to the Secretary, U.S. Nuclear Regulatory Commission, Washington, D.C., 20555-0001; Attention: Rulemaking and Adjudications Staff. Non-timely requests and/or petitions and contentions will not be entertained absent a determination by the Commission, the presiding officer, or the Atomic Safety and Licensing Board that the petition, request and/or contentions should be granted based on a balancing of the factors specified in 10 CFR 2.309(a)(1)(i)-(viii). Detailed information about the license renewal process can be found under the Nuclear Reactors icon at *http://www.nrc.gov/reactors/operating/licensing/renewal.html* on the NRC's Web site. Copies of the application to renew the operating license for Vermont Yankee Nuclear Power Station, are available for public inspection at the Commission's PDR, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland 20852-2738, and at *http://www.nrc.gov/reactors/operating/licensing/renewal/applications.html* , the NRC's Web site while the application is under review. The NRC maintains an Agencywide Documents Access and Management System (ADAMS), which provides text and image files of NRC's public documents. These documents may be accessed through the NRC's Public Electronic Reading Room on the Internet at *http://www.nrc.gov/reading-rm/adams.html* under ADAMS Accession Number ML060300085. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS may contact the NRC Public Document Room

(PDR)Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to *pdr@nrc.gov* . The staff has verified that a copy of the license renewal application is also available to local residents near the Vermont Yankee Nuclear Power Station at the Vernon Free Library, 567 Governor Hunt Road, Vernon, VT 05354; Brooks Memorial Library, 224 Main Street, Brattleboro, VT 05301; Hinsdale Public Library, 122 Brattleboro Road, Hinsdale, NH 03451; and Dickinson Memorial Library, 115 Main Street, Northfield, MA 01360. Dated at Rockville, Maryland, this 21st day of March, 2006. For the Nuclear Regulatory Commission. Frank P. Gillespie, Director, Division of License Renewal, Office of Nuclear Reactor Regulation. [FR Doc. E6-4381 Filed 3-24-06; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 50-293] Entergy Nuclear Operations, Inc., Pilgrim Nuclear Power Station; Notice of Acceptance for Docketing of the Application and Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License No. DPR-35 for an Additional 20-Year Period The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering an application for the renewal of Operating License No. DPR-35, which authorizes Entergy Nuclear Operations, Inc., to operate the Pilgrim Nuclear Power Station at 2028 megawatts

(MWt)thermal. The renewed license would authorize the applicant to operate the Pilgrim Nuclear Power Station for an additional 20 years beyond the period specified in the current license. The current operating license for the Pilgrim Nuclear Power Station expires on June 8, 2012. The Commission's staff received the application dated January 25, 2006, from Entergy Nuclear Operations, Inc., pursuant to 10 CFR Part 54, to renew the Operating License No. DPR-35 for Pilgrim Nuclear Power Station. A Notice of Receipt and Availability of the license renewal application, “Entergy Nuclear Operations, Inc., Notice of Receipt and Availability of Application for Renewal of Pilgrim Nuclear Power Station Facility Operating License No. PR-35 for an Additional 20-Year Period,” was published in the **Federal Register** on February 6, 2006 (71 FR 6101). The Commission's staff has determined that Entergy Nuclear Operations, Inc., has submitted sufficient information in accordance with 10 CFR 54.19, 54.21, 54.22, 54.23, and 51.53(c) and the application is acceptable for docketing. The current Docket No. 50-293 for Operating License No. DPR-35 will be retained. The docketing of the renewal application does not preclude requesting additional information as the review proceeds, nor does it predict whether the Commission will grant or deny the application. Before issuance of each requested renewed license, the NRC will have made the findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's rules and regulations. In accordance with 10 CFR 54.29, the NRC will issue a renewed license on the basis of its review if it finds that actions have been identified and have been or will be taken with respect to:

(1)Managing the effects of aging during the period of extended operation on the functionality of structures and components that have been identified as requiring aging management review, and

(2)time-limited aging analyses that have been identified as requiring review, such that there is reasonable assurance that the activities authorized by the renewed license will continue to be conducted in accordance with the current licensing basis (CLB), and that any changes made to the plant's CLB comply with the Act and the Commission's regulations. Additionally, in accordance with 10 CFR 51.95(c), the NRC will prepare an environmental impact statement that is a supplement to the Commission's NUREG-1437, “Generic Environmental Impact Statement for License Renewal of Nuclear Power Plants,” dated May 1996. Pursuant to 10 CFR 51.26, and as part of the environmental scoping process, the staff intends to hold a public scoping meeting. Detailed information regarding this meeting will be the subject of a separate **Federal Register** notice. Within 60 days after the date of publication of this **Federal Register** Notice, the applicant may file a request for a hearing, and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene with respect to the renewal of the license. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's “Rules of Practice for Domestic Licensing Proceedings” in 10 CFR Part 2. Interested persons should consult a current copy of 10 CFR 2.309, which is available at the Commission's Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike, first floor, Rockville, Maryland 20852 and is accessible from the Agencywide Documents Access and Management System (ADAMS) Public Electronic Reading Room on the Internet at *http://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's PDR reference staff by telephone at 1-800-397-4209, or by e-mail at *pdr@nrc.gov* . If a request for a hearing/petition for leave to intervene is filed within the 60-day period, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel will rule on the request/petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order. In the event that no request for a hearing/petition for leave to intervene is filed within the 60-day period, the NRC may, upon completion of its evaluations and upon making the findings required under 10 CFR Parts 51 and 54, renew the license without further notice. As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding, taking into consideration the limited scope of matters that may be considered pursuant to 10 CFR Parts 51 and 54. The petition must specifically explain the reasons why intervention should be permitted with particular reference to the following factors:

(1)The nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding;

(2)the nature and extent of the requestor's/petitioner's property, financial, or other interest in the proceeding; and

(1)Technical (primarily related to safety concerns);

(2)environmental; or

(1)First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff;

(2)courier, express mail, and expedited delivery services: Office of the Secretary, Sixteenth Floor, One White Flint North, 11555 Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and Adjudications Staff;

(3)e-mail addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, *HEARINGDOCKET@NRC.GOV* ; or

(4)facsimile transmission addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC, Attention: Rulemakings and Adjudications Staff at 301-415-1101, verification number is 301-415-1966. 2 A copy of the request for hearing and petition for leave to intervene must also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and it is requested that copies be transmitted either by means of facsimile transmission to 301-415-3725 or by e-mail to *OGCMailCenter@nrc.gov* . A copy of the request for hearing and petition for leave to intervene should also be sent to the attorney for the applicant, Mr. Terence A. Burke, Entergy Nuclear, 1340 Echelon Parkway, Mail Stop M-ECH-62, Jackson, MS 39213. 2 If the request/petition is filed by e-mail or facsimile, an original and two copies of the document must be mailed within 2

(two)business days thereafter to the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; Attention: Rulemaking and Adjudications Staff. Non-timely requests and/or petitions and contentions will not be entertained absent a determination by the Commission, the presiding officer, or the Atomic Safety and Licensing Board that the petition, request and/or contentions should be granted based on a balancing of the factors specified in 10 CFR 2.309(a)(1)(i)-(viii). Detailed information about the license renewal process can be found under the Nuclear Reactors icon at *http://www.nrc.gov/reactors/operating/licensing/renewal.html* on the NRC's Web site. Copies of the application to renew the operating license for Pilgrim Nuclear Power Station, are available for public inspection at the Commission's PDR, located at One White Flint North, 11555 Rockville Pike, first floor, Rockville, Maryland 20852-2738, and at *http://www.nrc.gov/reactors/operating/licensing/renewal/applications.html,* the NRC's Web site while the application is under review. The NRC maintains an Agencywide Documents Access and Management System (ADAMS), which provides text and image files of NRC's public documents. These documents may be accessed through the NRC's Public Electronic Reading Room on the Internet at *http://www.nrc.gov/reading-rm/adams.html* under ADAMS Accession Number ML060300024. Persons who do not have access to ADAMS or who encounter problems in accessing the documents located in ADAMS may contact the NRC Public Document Room

(PDR)Reference staff by telephone at 1-800-397-4209, 301-415-4737, or by e-mail to *pdr@nrc.gov* . The staff has verified that a copy of the license renewal application is also available to local residents near the Pilgrim Nuclear Power Station at the Plymouth Public Library, 132 South Street, Plymouth, MA 02360, and The Duxbury Free Library, 77 Alden Street, Duxbury, MA 02332. Dated at Rockville, Maryland, this 21st day of March, 2006. For the Nuclear Regulatory Commission. Frank P. Gillespie, Director, Division of License Renewal, Office of Nuclear Reactor Regulation. [FR Doc. E6-4382 Filed 3-24-06; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-321 and 50-366] Southern Nuclear Operating Company, Inc., Georgia Power Company,Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2; Notice of Consideration of Issuance of Amendments to Facility Operating Licenses, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to Facility Operating License Nos. DPR-57 and NPF-5, issued to Southern Nuclear Operating Company, Inc. (SNC, the licensee), for operation of the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2, located in Appling County, Georgia. The proposed amendment would add a license condition to Section 2.C of the Edwin I. Hatch Nuclear Plant, Unit Nos. 1 and 2, Operating Licenses. This license condition will authorize the licensee to credit administering potassium iodide

(KI)to reduce the 30-day post-accident thyroid radiological dose to the operators in the main control room

(MCR)for an interim period of approximately 4 years. In addition, the design-basis accident

(DBA)analysis section of the Updated Final Safety Analysis Reports will be updated to reflect crediting of KI. Before issuance of the proposed license amendments, 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), § 50.92, this means that operation of the facility in accordance with the proposed amendments 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: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? This proposed change will authorize SNC to credit KI for an interim period in the DBA radiological consequences analyses to address the impact of MCR unfiltered inleakage. This proposed change does not result in any functional or operational change to any systems, structures, or components and has no impact on any assumed initiator of any analyzed accident. Therefore, the proposed change does not result in an increase in the probability of an accident previously evaluated. This proposed change introduces an additional method of mitigating the thyroid dose to MCR occupants in the event of a loss-of-coolant accident (LOCA). The updated LOCA MCR radiological dose, considering 110 [cubic feet/minute] cfm unfiltered inleakage and crediting KI, continues to meet [General Design Criterion] GDC 19 acceptance limits. In the context of the current licensing basis with MCR unfiltered inleakage considered, LOCA continues to be the limiting event for radiological exposures to the operators in the MCR. Radiological doses to MCR occupants are within the regulatory limits of GDC 19 with MCR unfiltered inleakages of up to 1000 cfm without the crediting of KI for the main steam line break accident (MSLB), control rod drop accident (CRDA), and fuel handling accident (FHA). Therefore, the proposed change does not result in a significant increase in the consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any previously evaluated? This proposed change will authorize SNC to credit KI for an interim period in the [Design Basis Accident] DBA radiological consequences analyses to address the impact of MCR unfiltered inleakage. This proposed change does not result in any functional or operational change to any systems, structures, or components. 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 change involve a significant decrease in the margin of safety? This proposed change will authorize SNC to credit KI for an interim period in the DBA radiological consequences analyses to address the impact of MCR unfiltered inleakage. This proposed change does not result in any functional or operational change to any systems, structures, or components. This proposed change introduces an additional method of mitigating the thyroid dose to MCR occupants in the event of a LOCA. The updated LOCA MCR radiological dose, considering 110 cfm unfiltered inleakage and crediting KI, continues to meet GDC 19 acceptance limits. In the context of the current licensing basis with MCR unfiltered inleakage considered, LOCA continues to be the limiting event for radiological exposures to the operators in the MCR. Radiological doses to MCR occupants are within the regulatory limits of GDC 19 with MCR unfiltered inleakages of up to 1000 cfm without the crediting of KI for the main steam line break accident (MSLB), control rod drop accident (CRDA), and fuel handling accident (FHA). Therefore, the proposed change does not involve a significant decrease in the 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 60-day 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 the need to take this action will occur very infrequently. Written comments may be submitted by mail to the Chief, Rules and Directives Branch, Division of Administrative Services, Office of Administration, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and should cite the publication date and page number of this **Federal Register** notice. Written comments may also be delivered to Room 6D59, Two White Flint North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to 4:15 p.m. Federal workdays. Documents may be 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. The filing of requests for hearing and petitions for leave to intervene is discussed below. Within 60 days after the date of publication of this notice, the licensee may file a request for a hearing with respect to issuance of the amendment to the subject facility operating license and any person whose interest may be affected by this proceeding and who wishes to participate as a party in the proceeding must file a written request for a hearing and a petition for leave to intervene. Requests for a hearing and a petition for leave to intervene shall be filed in accordance with the Commission's “Rules of Practice for Domestic Licensing Proceedings” in 10 CFR part 2. Interested persons should consult a current copy of 10 CFR 2.309, which is available at the Commission's PDR, located at One White Flint North, Public File Area O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible from the Agencywide Documents Access and Management System's (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, *http://www.nrc.gov/reading-rm/doc-collections/cfr/* . If a request for a hearing or petition for leave to intervene is filed by the above date, the Commission or a presiding officer designated by the Commission or by the Chief Administrative Judge of the Atomic Safety and Licensing Board Panel, will rule on the request and/or petition; and the Secretary or the Chief Administrative Judge of the Atomic Safety and Licensing Board will issue a notice of a hearing or an appropriate order. As required by 10 CFR 2.309, a petition for leave to intervene shall set forth with particularity the interest of the petitioner in the proceeding, and how that interest may be affected by the results of the proceeding. The petition should specifically explain the reasons why intervention should be permitted with particular reference to the following general requirements:

(1)The name, address and telephone number of the requestor or petitioner;

(2)the nature of the requestor's/petitioner's right under the Act to be made a party to the proceeding;

(3)the nature and extent of the requestor's/petitioner's property, financial, or other interest in the proceeding; and

(4)the possible effect of any decision or order which may be entered in the proceeding on the requestors/petitioner's interest. The petition must also identify the specific contentions which the petitioner/requestor seeks to have litigated at the proceeding. Each contention must consist of a specific statement of the issue of law or fact to be raised or controverted. In addition, the petitioner/requestor shall provide a brief explanation of the bases for the contention and a concise statement of the alleged facts or expert opinion which support the contention and on which the petitioner intends to rely in proving the contention at the hearing. The petitioner/requestor must also provide references to those specific sources and documents of which the petitioner is aware and on which the petitioner intends to rely to establish those facts or expert opinion. The petition must include sufficient information to show that a genuine dispute exists with the applicant on a material issue of law or fact. Contentions shall be limited to matters within the scope of the amendment under consideration. The contention must be one which, if proven, would entitle the petitioner to relief. A petitioner/requestor who fails to satisfy these requirements with respect to at least one contention will not be permitted to participate as a party. Those permitted to intervene become parties to the proceeding, subject to any limitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing. If a hearing is requested, the Commission will make a final determination on the issue of no significant hazards consideration. The final determination will serve to decide when the hearing is held. If the final determination is that the amendment request involves no significant hazards consideration, the Commission may issue the amendment and make it immediately effective, notwithstanding the request for a hearing. Any hearing held would take place after issuance of the amendment. If the final determination is that the amendment request involves a significant hazards consideration, any hearing held would take place before the issuance of any amendment. Nontimely requests and/or petitions and contentions will not be entertained absent a determination by the Commission or the presiding officer of the Atomic Safety and Licensing Board that the petition, request and/or the contentions should be granted based on a balancing of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii). A request for a hearing or a petition for leave to intervene must be filed by:

(1)First class mail addressed to the Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemaking and Adjudications Staff;

(3)E-mail addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, *HEARINGDOCKET@NRC.GOV* ; or

(4)facsimile transmission addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC, Attention: Rulemakings and Adjudications Staff at

(301)415-1101, verification number is

(301)415-1966. A copy of the request for hearing and petition for leave to intervene should also be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and it is requested that copies be transmitted either by means of facsimile transmission to 301-415-3725 or by e-mail to *OGCMailCenter@nrc.gov.* A copy of the request for hearing and petition for leave to intervene should also be sent to Ernest L. Blake, Jr., Esquire, Shaw, Pittman, Potts and Trowbridge, 2300 N Street, NW., Washington, DC 20037, attorney for the licensee. For further details with respect to this action, see the application for amendment dated March 17, 2006, which is available for public inspection at the Commission's 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 from the Agencywide Documents Access and Management System's (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, *http://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, 301-415-4737, or by e-mail to *pdr@nrc.gov.* Dated at Rockville, Maryland, this 22nd day of March, 2006. For the Nuclear Regulatory Commission. Robert E. Martin, Senior Project Manager, Plant Licensing Branch II-1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E6-4372 Filed 3-24-06; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket Nos. (as shown in Attachment 1); License Nos. (as shown in Attachment 1); EA-06-037] In the Matter of Operating Power Reactor Licensees Identified in Attachment 1; Order Modifying Licenses (Effective Immediately) I. The licensees identified in Attachment 1 to this Order hold licenses issued by the U.S. Nuclear Regulatory Commission (NRC or the Commission) authorizing operation of nuclear power plants in accordance with the Atomic Energy Act of 1954 and Title 10 of the Code of Federal Regulations (10 CFR) part 50. Commission regulations at 10 CFR 50.54(p)(1) require these licensees to maintain safeguards contingency plan procedures in accordance with 10 CFR part 73, Appendix C. Specific safeguards requirements for reactors are contained in 10 CFR 73.55. II. On September 11, 2001, terrorists simultaneously attacked targets in New York, N.Y., and Washington, DC, using large commercial aircraft as weapons. In response to the attacks and intelligence information subsequently obtained, the Commission issued a number of Safeguards and Threat Advisories to its licensees, and eventually Orders to selected licensees, to strengthen licensees' capabilities and readiness to respond to a potential attack on a nuclear facility. On April 29, 2003, the Commission issued an Order to all operating power reactor licensees that enhanced the design basis threat

(DBT)specified in 10 CFR 73.1. As a result of the Commission's continued assessment of threat information, the Commission has determined that a revision to one of the specific adversary characteristics set forth in the April 29, 2003, DBT Order needs to be updated and enhanced. The update to the adversary characteristic is set forth in Attachment 2 1 of this Order. Each licensee must amend its site security plans to address the new adversary characteristic in its protective strategy. 1 Attachment 2 contains Safeguards Information and will not be publicly disclosed. Any needed changes to the physical security plan, safeguards contingency plan, or guard training and qualification plan required by 10 CFR 50.34(c), 50.34(d), and 73.55(b)(4)(ii), respectively, shall be completed and implemented within 60 days of the date of this Order. Pursuant to 10 CFR 2.202, I find that in the circumstances described above, the public health, safety, and interest and the common defense and security require that this Order be immediately effective. III. Accordingly, pursuant to Sections 103, 104, 161b, 161i, 161o, 182, and 186 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202 and 10 CFR parts 50 and 73, it is hereby ordered, effective immediately, that all licenses identified in Attachment 1 to this order are modified as follows: A.1. Each licensee shall revise its physical security plan and safeguards contingency plan, prepared pursuant to 10 CFR 50.34(c) and 50.34(d), to provide protection against the updated adversary characteristic set forth in Attachment 2 to this Order. In addition, each licensee shall revise its training and qualification plan, required by 10 CFR 73.55(b)(4)(ii), to implement the updated adversary characteristic set forth in Attachment 2 to this Order. 2. Each licensee shall implement necessary changes to its physical security plan, safeguards contingency plan, and guard training and qualification plan no later than 60 days from the date of this Order. B.1. Each licensee shall, within twenty-one

(21)days of the date of this Order, notify the Commission:

(1)If the licensee is unable to comply with any requirement of this Order,

(2)if compliance with any requirement of this Order is unnecessary in the licensee's specific circumstances, or

(3)if implementation of any requirement of this Order would cause the licensee to be in violation of the provisions of any Commission regulation or the facility license. The notification shall provide the licensee's justification for seeking relief from, or variation of, any specific requirement. 2. Any licensee that considers that implementation of any of the requirements of this Order would adversely impact safe operation of the facility must notify the Commission, within twenty-one

(21)days of this Order, of the adverse safety impact, the basis for its determination that the requirement has an adverse safety impact, and either a proposal for achieving the same objectives of this Order, or a schedule for modifying the facilities to address the adverse safety condition. If neither approach is appropriate, the licensee must supplement its response to Condition B.1. of this Order to identify the condition as a requirement with which it cannot comply, with attendant justifications as required in Condition B.1. C. Each licensee shall report to the Commission, in writing, when it has fully implemented this Order. The notification shall be made no later than 60 days from the date of the Order and include substitute security plan pages that reflect any changes made to implement the Order. D. All measures implemented or actions taken in response to this Order shall be maintained until the Commission determines otherwise, except that the licensee may change its revised physical security plans, safeguards contingency plans, and guard training and qualification plans if authorized by 10 CFR 50.54(p). Licensee responses to Conditions A.1, B.1, B.2, and C above, shall be submitted in accordance with 10 CFR 50.4. In addition, licensee submittals that contain safeguards information shall be properly marked and handled in accordance with 10 CFR 73.21. The Director, Office of Nuclear Reactor Regulation, may, in writing, relax or rescind any of the above conditions upon demonstration by the licensee of good cause. IV. In accordance with 10 CFR 2.202, the licensee must, and any other person adversely affected by this Order may, submit an answer to this Order, and may request a hearing on this Order, within twenty-one

(21)days of the date of this Order. Where good cause is shown, consideration will be given to extending the time to request a hearing. A request for an extension of time in which to submit an answer or request a hearing must be made in writing to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, and include a statement of good cause for the extension. The answer may consent to this Order. Unless the answer consents to this Order, the answer shall, in writing and under oath or affirmation, specifically set forth the matters of fact and law on which the licensee or other person adversely affected relies and the reasons as to why the Order should not have been issued. Any answer or request for a hearing shall be submitted to the Secretary, Office of the Secretary of the Commission, U.S. Nuclear Regulatory Commission, ATTN: Rulemakings and Adjudications Staff, Washington, DC 20555-0001. Copies also shall be sent to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001; to the Assistant General Counsel for Materials Litigation and Enforcement at the same address; to the Regional Administrator for NRC Region I, II, III, or IV, as appropriate for the specific facility; and to the licensee if the answer or hearing request is by a person other than the licensee. Because of possible delays in delivery of mail to United States Government offices, it is requested that answers and requests for hearing be transmitted to the Secretary of the Commission either by means of facsimile transmission to 301-415-1101 or by e-mail to *hearingdocket@nrc.gov* and also to the Office of the General Counsel either by means of facsimile transmission to 301-415-3725 or by e-mail to *OGCMailCenter.gov* . If a person other than the licensee requests a hearing, that person shall set forth with particularity the manner in which his or her interest is adversely affected by this Order and shall address the criteria set forth in 10 CFR 2.309(d). If a hearing is requested by the licensee or a person whose interest is adversely affected, the Commission will issue an Order designating the time and place of any hearing. If a hearing is held, the issue to be considered at such hearing shall be whether this Order should be sustained. Pursuant to 10 CFR 2.202(c)(2)(i), the licensee may, in addition to demanding a hearing, at the time the answer is filed or sooner, move the presiding officer to set aside the immediate effectiveness of the Order on the ground that the Order, including the need for immediate effectiveness, is not based on adequate evidence but on mere suspicion, unfounded allegations, or error. In the absence of any request for hearing, or written approval of an extension of time in which to request a hearing, the provisions specified in Section III above shall be final twenty-one

(21)days from the date of this Order without further order or proceedings. If an extension of time for requesting a hearing has been approved, the provisions specified in Section III shall be final when the extension expires if a hearing request has not been received. An answer or a request for hearing shall not stay the immediate effectiveness of this order. For the Nuclear Regulatory Commission. Dated this 20th day of March 2006. J.E. Dyer, Director, Office of Nuclear Reactor Regulation. Attachment 1—List of Addressees; Power Plants—Senior Executive/Security Contacts Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC-N09 Salem Nuclear Generating Station, Units 1 & 2 Docket Nos. 50-272 & 50-311 License Nos. DPR-70 & DPR-75 End of Buttonwood Road Hancocks Bridge, NJ 08038 Mr. William Levis Senior Vice President & Chief Nuclear Officer PSEG Nuclear LLC-X15 Hope Creek Generating Station, Unit 1 Docket No. 50-354 License No. NPF-57 End of Buttonwood Road Hancocks Bridge, NJ 08038 Mr. Michael Kansler President Entergy Nuclear Operations, Inc. Pilgrim Nuclear Power Station, Unit 1 Docket No. 50-293 License No. DPR-35 440 Hamilton Avenue White Plains, NY 10601 Mr. Michael Kansler President Entergy Nuclear Operations, Inc. Vermont Yankee Nuclear Power Station Docket No. 50-271 License No. DPR-28 440 Hamilton Avenue White Plains, NY 10601 Mr. Michael Kansler President Entergy Nuclear Operations, Inc. James A. FitzPatrick Nuclear Power Plant Docket No. 50-333 License No. DPR-59 440 Hamilton Avenue White Plains, NY 10601 Mr. Michael Kansler President Entergy Nuclear Operations, Inc. Indian Point Nuclear Generating Station, Units 2 & 3 Docket Nos. 50-247 & 50-286 License Nos. DPR-26 & DPR-64 440 Hamilton Avenue White Plains, NY 10601 Mr. Gene St. Pierre Site Vice President FPL Energy Seabrook Station, Unit 1 Docket No. 50-443 License No. NPF-86 Central Receiving, Lafayette Road Seabrook, NH 03874 Mr. James H. Lash Vice President FirstEnergy Nuclear Operating Company Beaver Valley Power Station, Units 1 & 2 Docket Nos. 50-334 & 50-412 License Nos. DPR-66 & NPF-73 Route 168 Shippingport, PA 15077 Mr. James A. Spina Vice President Calvert Cliffs Nuclear Power Plant, Inc. Calvert Cliffs Nuclear Power Plant, Units 1 & 2 Docket Nos. 50-317 & 50-318 License Nos. DPR-53 & DPR-69 1650 Calvert Cliffs Parkway Lusby, MD 20657-4702 Mrs. Mary G. Korsnick Vice President R. E. Ginna Nuclear Power Plant, LLC Docket No. 50-244 License No. DPR-18 1503 Lake Road Ontario, NY 14519-9364 Mr. Timothy J. O'Connor Vice President Nine Mile Point Nuclear Station, LLC Nine Mile Point Nuclear Station, Units 1 & 2 Docket Nos. 50-220 & 50-410 License Nos. DPR-63 & NPF-69 348 Lake Road Oswego, NY 13126 Mr. Britt T. McKinney Sr. Vice President & Chief Nuclear Officer PPL Susquehanna, LLC Susquehanna Steam Electric Station, Units 1 & 2 Docket Nos. 50-387 & 50-388 License Nos. NPF-14 & NPF-22 769 Salem Boulevard, NUCSB3 Berwick, PA 18603-0467 Mr. David A. Christian Sr. Vice President & Chief Nuclear Officer Dominion Nuclear Connecticut, Inc. Millstone Power Station, Units 2 & 3 Docket Nos. 50-336 & 50-423 License Nos. DPR-65 & NPF-49 Innsbrook Technical Center, 5000 Dominion Boulevard Glen Allen, VA 23060 Mr. David A. Christian Sr. Vice President & Chief Nuclear Officer Virginia Electric and Power Company North Anna Power Station, Units 1 & 2 Docket Nos. 50-338 & 50-339 License Nos. NPF-4 & NPF-7 Innsbrook Technical Center, 5000 Dominion Boulevard Glen Allen, VA 23060 Mr. David A. Christian Sr. Vice President & Chief Nuclear Officer Virginia Electric and Power Company Surry Power Station, Units 1 & 2 Docket Nos. 50-280 & 50-281 License Nos. DPR-32 & DPR-37 Innsbrook Technical Center, 5000 Dominion Boulevard Glen Allen, VA 23060 Mr. David A. Christian Sr. Vice President & Chief Nuclear Officer Dominion Energy Kewaunee, Inc. Kewaunee Nuclear Power Plant Docket No. 50-305 License No. DPR-43 Innsbrook Technical Center 5000 Dominion Boulevard Glen Allen, VA 23060 Mr. Dhiaa M. Jamil Vice President Duke Energy Corporation Catawba Nuclear Station, Units 1 & 2 Docket Nos. 50-413 & 50-414 License Nos. NPF-35 & NPF-52 4800 Concord Road York, SC 29745 Mr. L. M. Stinson Vice President—Farley Project Southern Nuclear Operating Company, Inc. Joseph M. Farley Nuclear Plant, Units 1& 2 Docket Nos. 50-348 & 50-364 License Nos. NPF-2 & NPF-8 40 Inverness Center Parkway Birmingham, AL 35242 Mr. H. L. Sumner, Jr. Vice President—Nuclear, Hatch Project Southern Nuclear Operating Company, Inc. Edwin I. Hatch Nuclear Plant, Units 1 & 2 Docket Nos. 50-321 & 50-366 License Nos. DPR-57 & NPF-5 40 Inverness Center Parkway Birmingham, AL 35242 Mr. G. R. Peterson Vice President Duke Energy Corporation William B. McGuire Nuclear Station, Units 1 & 2 Docket Nos. 50-369 & 50-370 License Nos. NPF-9 & NPF-17 12700 Hagers Ferry Road Huntersville, NC 28078 Mr. Bruce H. Hamilton Vice President, Oconee Site Duke Energy Corporation Oconee Nuclear Station, Units 1, 2 & 3 Docket Nos. 50-269, 50-270 & 50-287 License Nos. DPR-38, DPR-47 & DPR-55 7800 Rochester Highway Seneca, SC 29672 Mr. Don E. Grissette Vice President Southern Nuclear Operating Company, Inc. Vogtle Electric Generating Plant, Units 1 & 2 Docket Nos. 50-424 & 50-425 License Nos. NPF-68 & NPF-81 40 Inverness Center Parkway Birmingham, AL 35242 Mr. James Scarola Vice President Carolina Power & Light Company Progress Energy, Inc. Brunswick Steam Electric Plant, Units 1 & 2 Docket Nos. 50-325 & 50-324 License Nos. DPR-71 & DPR-62 Hwy 87, 2.5 Miles North Southport, NC 28461 Mr. C.J. Gannon Vice President Carolina Power & Light Company Shearon Harris Nuclear Power Plant, Unit 1 Docket No. 50-400 License No. NPF-63 5413 Shearon Harris Road New Hill, NC 27562-0165 Mr. Dale E. Young Vice President Supervisor, Licensing & Regulatory Programs Florida Power Corporation Crystal River Nuclear Generating Plant, Unit 3 Docket No. 50-302 License No. DPR-72 15760 W. Power Line Street Crystal River, FL 34428-6708 Mr. J. W. Moyer Vice President Carolina Power & Light Company Progress Energy H. B. Robinson Steam Electric Plant, Unit 2 Docket No. 50-261 License No. DPR-23 3581 West Entrance Road Hartsville, SC 29550 Mr. Brian J. O'Grady Site Vice President Browns Ferry Nuclear Plant, Units 1, 2 & 3 Tennessee Valley Authority Docket Nos. 50-259, 50-260 & 50-296 License Nos. DPR-33, DPR-52 & DPR-68 10835 Shaw Rd. Athens, AL 35611 Mr. Michael Skaggs Site Vice President Watts Bar Nuclear Plant, Unit 1 Tennessee Valley Authority Docket No. 50-390 License No. NPF-90 Highway 68 Near Spring City Spring City, TN 37381 Mr. Randy Douet Site Vice President Sequoyah Nuclear Plant, Units 1 & 2 Tennessee Valley Authority Docket Nos. 50-327 & 50-328 License Nos. DPR-77 & DPR-79 2000 Igou Ferry Road Soddy Daisy, TN 37379 Mr. J. A. Stall Senior Vice President, Nuclear & Chief Nuclear Officer Florida Power and Light Company St. Lucie, Units 1 & 2 Docket Nos. 50-335 & 50-389 License Nos. DPR-67 & NPF-16 700 Universe Boulevard Juno Beach, FL 33408-0420 Mr. J. A. Stall Senior Vice President, Nuclear and Chief Nuclear Officer Florida Power and Light Company Turkey Point Nuclear Generating Station, Units 3 and 4 Docket Nos. 50-250 & 50-251 License Nos. DPR-31 & DPR-41 700 Universe Boulevard Juno Beach, FL 33408-0420 Mr. Mano K. Nazar Senior Vice President & Chief Nuclear Officer Indiana Michigan Power Company Nuclear Generation Group Donald C. Cook Nuclear Plant, Units 1 and 2 Docket Nos. 50-315 & 50-316 License Nos. DPR-58 & DPR-74 One Cook Place Bridgman, MI 49106 Mr. Gary Van Middlesworth Site Vice President FLP Energy Duane Arnold Energy Center Docket No. 50-331 License No. DPR-49 3277 DAEC Road Palo, IA 52324-9785 Mr. Donald K. Cobb Assistant Vice President—Nuclear Generation Detroit Edison Company Fermi, Unit 2 Docket No. 50-341 License No. NPF-43 6400 North Dixie Highway Newport, MI 48166 Mr. John Conway Site Vice President Nuclear Management Company, LLC Monticello Nuclear Generating Plant Docket No. 50-263 License No. DPR-22 2807 West County Road 75 Monticello, MN 55362-9637 Paul A. Harden Site Vice President Nuclear Management Company, LLC Palisades Nuclear Plant Docket No. 50-255 License No.DPR-20 27780 Blue Star Memorial Highway Covert, MI 49043-9530 Mr. Dennis L. Koehl Site Vice President Nuclear Management Company, LLC Point Beach Nuclear Plant, Units 1 & 2 Docket Nos. 50-266 & 50-301 License Nos. DPR-24 & DPR-27 6590 Nuclear Road Two Rivers, WI 54241-9516 Mr. Thomas J. Palmisano Site Vice President Nuclear Management Company, LLC Prairie Island Nuclear Generating Plant, Units 1 & 2 Docket Nos. 50-282 & 50-306 License Nos. DPR-42 & DPR-60 1717 Wakonade Drive East Welch, MN 55089 Mr. Christopher M. Crane President & Chief Nuclear Officer Exelon Generation Company, LLC Braidwood Station, Units 1 & 2 Docket Nos. 50-456 & 50-457 License Nos. NPF-72 & NPF-77 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer Exelon Generation Company, LLC Byron Station, Units 1 & 2 Docket Nos. 50-454 & 50-455 License Nos. NPF-37 & NPF-66 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer Exelon Generation Company, LLC Dresden Nuclear Power Station, Units 2 & 3 Docket Nos. 50-237 & 50-249 License Nos. DPR-19 & DPR-25 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer Exelon Generation Company, LLC LaSalle County Station, Units 1 & 2 Docket Nos. 50-373 & 50-374 License Nos. NPF-11 & NPF-18 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer Exelon Generation Company, LLC Quad Cities Nuclear Power Station, Units 1 & 2 Docket Nos. 50-254 & 50-265 License Nos. DPR-29 & DPR-30 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer Exelon Generation Company, LLC Limerick Generating Station, Units 1 & 2 Docket Nos. 50-352 & 50-353 License Nos. NPF-39 & NPF-85 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer Exelon Generation Company, LLC Peach Bottom Atomic Power Station, Units 2 & 3 Docket Nos. 50-277 & 50-278 License Nos. DPR-44 & DPR-56 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer AmerGen Energy Company, LLC Oyster Creek Nuclear Generating Station Docket No. 50-219 License No. DPR-16 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer AmerGen Energy Company, LLC Clinton Power Station Docket No. 50-461 License No. NPF-62 4300 Winfield Road Warrenville, IL 60555 Mr. Christopher M. Crane President & Chief Nuclear Officer AmerGen Energy Company, LLC Three Mile Island Nuclear Station, Unit 1 Docket No. 50-289 License No. DPR-50 4300 Winfield Road Warrenville, IL 60555 Mr. Mark Bezilla Vice President, Davis-Besse FirstEnergy Nuclear Operating Company Davis-Besse Nuclear Power Station Docket No. 50-346 License No. NPF-3 5501 North State Route 2 Oak Harbor, OH 43449-9760 Mr. L.W. Pearce Vice President—Nuclear, Acting FirstEnergy Nuclear Operating Company Perry Nuclear Power Plant, Unit 1 Docket No. 50-440 License No. NPF-58 10 North Center Street Perry, OH 44081 Mr. Jeffrey S. Forbes Site Vice President Entergy Operations, Inc. Arkansas Nuclear One, Units 1 & 2 Docket Nos. 50-313 & 50-368 License Nos. DPR-51 & NPF-6 1448 S. R. 333 Russellville, AR 72802 M. R. Blevins Senior Vice President and Chief Nuclear Officer TXU Generation Company, LP Comanche Peak Steam Electric Station, Units 1 & 2 Docket Nos. 50-445 & 50-446 License Nos. NPF-87 & NPF-89 5 Miles North of Glen Rose Glen Rose, TX 76043 Mr. Randall K. Edington Vice President—Nuclear and CNO Nebraska Public Power District Cooper Nuclear Station Docket No. 50-298 License No. DPR-46 1200 Prospect Road Brownville, NE 68321 Mr. George A. Williams GGNS Vice President, Operations Entergy Operations, Inc. Grand Gulf Nuclear Station, Unit 1 Docket No. 50-416 License No. NPF-29 7003 Bald Hill Road-Waterloo Road Port Gibson, MS 39150 Mr. Paul D. Hinnenkamp Vice President—Operations Entergy Operations, Inc. River Bend Station, Unit 1 Docket No. 50-458 License No. NPF-47 5485 U.S. Highway 61N St. Francisville, LA 70775 Mr. James J. Sheppard President & Chief Executive Officer South Texas Nuclear Operating Company South Texas Project, Units 1 & 2 Docket Nos. 50-498 & 50-499 License Nos. NPF-76 & NPF-80 8 Miles West of Wadsworth, on FM 521 Wadsworth, TX 77483 Mr. Joseph E. Venable Vice President Operations Entergy Operations, Inc. Waterford Steam Electric Generating Station, Unit 3 Docket No. 50-382 License No. NPF-38 17265 River Road Killona, LA 70057-3093 Mr. Charles D. Naslund Senior Vice President & Chief Nuclear Officer Union Electric Company Callaway Plant, Unit 1 Docket No. 50-483 License No. NPF-30 Junction Hwy CC & Hwy O: 5 Miles North of Hwy 94 Portland, MO 65067 Mr. John S. Keenan Senior Vice President, Generation and Chief Nuclear Officer Pacific Gas and Electric Company Diablo Canyon Nuclear Power Plant, Units 1 & 2 Docket Nos. 50-275 & 50-323 License Nos. DPR-80 & DPR-82 77 Beale Street, Mail Code B32 San Francisco, CA 94105 Mr. R. T. Ridenoure Vice President—Chief Nuclear Officer Omaha Public Power District Fort Calhoun Station, Unit 1 Docket No. 50-285 License No. DPR-40 Fort Calhoun Station Administration Building 9750 Power Lane Blair, NE 68008 Mr. James M. Levine Executive Vice President, Generation Arizona Public Service Company Palo Verde Nuclear Generating Station, Units 1, 2 and 3 Docket Nos. 50-528, 50-529 & 50-530 License Nos. NPF-41, NPF-51 & NPF-74 5801 S. Wintersburg Road Tonopah, AZ 85354-7529 Mr. Richard M. Rosenblum Chief Nuclear Officer Southern California Edison Company San Onofre Nuclear Station, Units 2 & 3 Docket Nos. 50-361 & 50-362 License Nos. NPF-10 & NPF-15 5000 Pacific Coast Highway San Clemente, CA 92674 Mr. J. V. Parrish Chief Executive Officer Energy Northwest Columbia Generating Station Docket No. 50-397 License No. NPF-21 Snake River Warehouse North Power Plant Loop Richland, WA 99352 Mr. Rick A. Muench President & Chief Executive Officer Wolf Creek Nuclear Operating Corporation Wolf Creek Generating Station, Unit 1 Docket No. 50-482 License No. NPF-42 1550 Oxen Lane, NE Burlington, KS 66839 Mr. Jeffrey B. Archie Vice President, Nuclear Operations South Carolina Electric and Gas Company Virgil C. Summer Nuclear Station Docket No. 50-395 License No. NPF-12 Hwy 215N at O.S. Bradham Boulevard Jenkinsville, SC 29065 [FR Doc. E6-4371 Filed 3-24-06; 8:45 am] BILLING CODE 7590-01-P POSTAL RATE COMMISSION Sunshine Act; Notice of Meetings name of agency: Postal Rate Commission. time and date: 10 a.m., Tuesday, March 28, 2006. place: Commission conference room, 901 New York Avenue, NW., Suite 200, Washington, DC 20268-0001. status: Closed. matters to be considered: Personnel issues. FOR FURTHER INFORMATION CONTACT: Steven W. Williams, Secretary, 202-789-6842. Dated: March 23, 2006. Steven W. Williams, Secretary. [FR Doc. 06-2963 Filed 3-23-06; 11:06 am]

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