Notices. Notice of consideration of approval of proposed corporate restructuring and opportunity for hearing

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BILLING CODE 7555-01-M NUCLEAR REGULATORY COMMISSION [Docket No 72-17] Portland General Electric Company, Trojan Nuclear Plant, Independent Spent Fuel Storage Installation; Notice of Consideration of Approval of Proposed Corporate Restructuring And Opportunity For A Hearing AGENCY: Nuclear Regulatory Commission. ACTION: Notice of consideration of approval of proposed corporate restructuring and opportunity for hearing. FOR FURTHER INFORMATION CONTACT: Christopher M. Regan, Senior Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555. Telephone:

(301)415-1179; fax number:

(301)415-1179; e-mail: *cmr1@nrc.gov.* SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (the Commission or NRC) is considering the issuance of an order under 10 CFR 72.50 approving the indirect transfer of Special Nuclear Materials License No.

(SNM)-2509 for the Trojan Independent Spent Fuel Storage Installation (ISFSI) currently held by PacifiCorp Holdings, Inc. (PacifiCorp) as minority owner and non-operating licensee of the Trojan ISFSI. The indirect transfer would be to MidAmerican Energy Holdings Company (MidAmerican). The indirect transfer will occur in connection with the sale of PacifiCorp, a wholly-owned indirect subsidiary of Scottish Power plc, to NWQ, LLC, a Delaware limited liability corporation and a wholly-owned subsidiary of MidAmerican. PacifiCorp will continue to be a 2.5% non-operating licensee of the Trojan ISFSI and as such PacifiCorp's license is not being transferred to another party. Instead, under the transaction, MidAmerican will acquire all of the issued and outstanding common stock of PacifiCorp. According to an application for approval filed by PacifiCorp, MidAmerican would acquire all of the issued and outstanding common stock of Pacificorp to the Trojan ISFSI following approval of the proposed indirect license transfer. No physical changes to the Trojan ISFSI or operational changes are being proposed in the application. Pursuant to 10 CFR 72.50, no license, or any part included in the license issued under 10 CFR Part 72 for an ISFSI shall be transferred, assigned, or in any manner disposed of, either voluntarily or involuntarily, directly or indirectly, through transfer of control of the license to any person unless the Commission gives its consent in writing. The Commission will approve an application for the indirect transfer of a license, if the Commission determines that the proposed transferee is qualified to hold the license, and that the transfer is otherwise consistent with applicable provisions of law, regulations, and orders issued by the Commission pursuant thereto. As provided in 10 CFR 2.1315, unless otherwise determined by the Commission with regard to a specific application, the Commission has determined that any motion relevant to the license of an ISFSI which does no more than reflect the indirect transfer action involves no genuine issue as to whether the health and safety of the public will be significantly affected. No contrary determination has been made with respect to this specific application. In light of the generic determination reflected in 10 CFR 2.1315, no public comments with respect to such determinations are being solicited. The filing of requests for hearing and petitions for leave to intervene, and written comments with regard to the indirect license transfer application, are discussed below. Within 20 days after the date of publication of this notice, the licensee may file a request for a hearing with respect to issuance of approval of the indirect transfer for the subject ISFSI 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 petitions for leave to intervene shall be filed in accordance with the Commission's rules of practice set forth in Subpart M, “Hearing Requests and Procedures for Hearings on License Transfer Applications,” of 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, Public File Area 01F21, 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 within 20 days after the date of publication of this notice, 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/ requestor 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/requestor 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/requestor 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. Non-timely 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(a)(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;

(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. 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.* Requests for a hearing and petitions for leave to intervene should be served upon Douglas L. Anderson and Jon A. Andreasen of MidAmerican Energy Holdings Company, 666 Grand Avenue, Des Moines, Iowa 50303; M. Douglas Dunn, Steven M Kramer, and Carla J. Urquhart of Milbank, Tweed, Hadley & McCloy L.L.P., 1 Chase Manhatten Plaza, New York, New York, 10005, ph.:

(212)530-5000; Jeffery B. Erb of PacifiCorp, Suite 1900, 825 N.E. Multnomah, Portland, Oregon, 92732; and Sam Behrends IV and Robert M. Andersen of LeBoeuf, Lamb, Greene & MacRae, L.L.P., 1875 Connecticut Avenue, NW., Suite 1200, Washington, DC 20009-5728, ph.:

(202)986-8000, facsimile: (202)986-8102. The Commission will issue a notice or order granting or denying a hearing request or intervention petition, designating the issues for any hearing that will be held, and designating the presiding officer. A notice granting a hearing will be published in the **Federal Register** and served on the parties to the hearing. As an alternative to requests for hearing and petitions to intervene, by August 26, 2005, persons may submit written comments regarding the license transfer application, as provided for in 10 CFR 2.1305. The Commission will consider and, if appropriate, respond to these comments, but such comments will not otherwise constitute part of the decisional record. Comments should be submitted to the Secretary, U.S. Nuclear Regulatory Commission, Washington, DC 20555-0001, Attention: Rulemakings and Adjudications Staff, and should cite the publication date and page number of this **Federal Register** notice. Further Information For further details with respect to this action, see the application dated June 30, 2005, 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. Publicly available records will be accessible electronically 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.* For The Nuclear Regulatory Commission. Dated in Rockville, Maryland this 20th day of July 2005. Christopher M. Regan, Senior Project Manager, Licensing Section, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards. [FR Doc. E5-3994 Filed 7-26-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 50-261] Carolina Power And Light Company, H. B. Robinson Steam Electric Plant, Unit No. 2; Environmental Assessment and Finding of No Significant Impact The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering issuance of an exemption from Title 10 of the Code of Federal Regulations (10 CFR) part 50, section 68, “Criticality Accident Requirements,” subsection (b)(1) for Facility Operating License No. DPR-23 issued to the Carolina Power and Light Company (the licensee) for operation of the H.B. Robinson Steam Electric Plant, Unit No. 2 (HBRSEP2) located in Darlington County, South Carolina. The NRC is issuing this environmental assessment pursuant to 10 CFR 51.21 and is making a finding of no significant impact (FONSI). Environmental Assessment Identification of the Proposed Action The proposed action would exempt the licensee from the requirements of 10 CFR 50.68, “Criticality Accident Requirements,” subsection (b)(1) during the spent fuel pool activities related to the underwater handling, loading, and unloading of the dry shielded canister

(DSC)NUHOMS -24PTH as described in proposed Amendment No. 8 to Certificate of Compliance No. 1004 listed in 10 CFR 72.214. The proposed action is in accordance with the licensee's application dated February 22, 2005, as supplemented on May 10 and July 6, 2005. The Need for the Proposed Action In 10 CFR 50.68(b)(1), the Commission sets forth the following requirement that must be met in lieu of a monitoring system capable of detecting criticality events: Plant procedures shall prohibit the handling and storage at any one time of more fuel assemblies than have been determined to be safely subcritical under the most adverse moderation conditions feasible by unborated water. Section 50.12(a) of 10 CFR allows licensees to request an exemption from the requirements of 10 CFR Part 50 if the application of the regulation is not necessary to achieve the underlying purpose of the rule and special conditions are met. The licensee stated that compliance with 10 CFR 50.68(b)(1) is not necessary for underwater handling, loading, and unloading of the DSC NUHOMS-24PTH in the HBRSEP2 spent fuel pool to achieve the underlying purpose of the rule. The NRC has completed its safety evaluation of the proposed action and concludes that the underlying purpose of 10 CFR 50.68(b)(1) will still be satisfied if the exemption is granted. The details of the NRC staff's safety evaluation will be provided in the exemption that will be issued as part of the letter to the licensee approving the exemption to the regulation. Environmental Impacts of the Proposed Action The proposed action will not significantly increase the probability or consequences of accidents. No changes are being made in the types of effluents that may be released off site. There is no significant increase in the amount of any effluent released off site. There is no significant increase in occupational or public radiation exposure. Therefore, there are no significant radiological impacts associated with the proposed action. With regard to potential non-radiological impacts, the proposed action does not have a potential to affect any historic sites. It does not affect non-radiological plant effluents and has no other environmental impact. Therefore, there are no significant non-radiological impacts associated with the proposed action. Accordingly, the NRC concludes that there are no significant environmental impacts associated with the proposed action. Environmental Impacts of the Alternatives to the Proposed Action As an alternative to the proposed action, the staff considered denial of the proposed action ( *i.e.* , the “no-action” alternative). Denial of the application would result in no change in current environmental impacts. The environmental impacts of the proposed action and the alternative action are similar. Alternative Use of Resources The action does not involve the use of any different resources than those previously considered in the Final Environmental Statement for HBRSEP2 dated April 1975, and the Final Supplemental Environmental Impact Statement (NUREG-1437 Supplement 13) dated December 2003. Agencies and Persons Consulted On July 11, 2005, the staff consulted with the South Carolina State official, Mr. Michael Gandy of the South Carolina Department of Health, regarding the environmental impact of the proposed action. The State official had no comments. Finding of No Significant Impact On the basis of the environmental assessment set forth above, the NRC concludes that the proposed action will not have a significant effect on the quality of the human environment and is therefore issuing this FONSI. Accordingly, the NRC has determined not to prepare an environmental impact statement for the proposed action. For further details with respect to the proposed action, see the licensee's letters dated February 22, May 10, and July 6, 2005. Documents may be examined, and/or copied for a fee, at the NRC's Public Document Room (PDR), located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management System (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 at 1-800-397-4209 or 301-415-4737, or send an e-mail to *pdr@nrc.gov.* Dated in Rockville, Maryland, this 20th day of July, 2005. For The Nuclear Regulatory Commission. Chandu P. Patel, Project Manager, Section 2, Project Directorate II, Division of Licensing Project Management, Office of Nuclear Reactor Regulation. [FR Doc. E5-3995 Filed 7-26-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 72-13] Entergy Operations, Inc., Arkansas Nuclear One Independent Spent Fuel Storage Installation; Issuance of Environmental Assessment and Finding of No Significant Impact Regarding a Proposed Exemption AGENCY: Nuclear Regulatory Commission. ACTION: Issuance of Environmental Assessment and Finding of No Significant Impact. FOR FURTHER INFORMATION CONTACT: Christopher M. Regan, Senior Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC. 20555. Telephone:

(301)415-1179; fax number:

(301)415-1179; e-mail: *cmr1@nrc.gov.* SUPPLEMENTARY INFORMATION: The U.S. Nuclear Regulatory Commission (NRC or Commission) is considering a request dated March 21, 2005, from Entergy Operations, Inc. (applicant or Entergy Operations) for exemption from the requirements of 10 CFR 72.212(a)(2) and 10 CFR 72.214 pursuant to 10 CFR 72.7, for the Arkansas Nuclear One (ANO), Unit 1 and Unit 2 Independent Spent Fuel Storage Installation, located 6 miles west-northwest of Russellville, Arkansas. In consideration of the request, the NRC would also grant exemption from the requirements of 10 CFR 72.212(b)(2)(I) and 72.212(b)(7). The exemption would authorize the applicant to store damaged spent nuclear fuel

(SNF)assemblies in a Holtec HI-STORM 100, Amendment 1 design, Multi-Purpose Canister

(MPC)-32. Environmental Assessment

(EA)I. Identification of Proposed Action By letter dated March 21, 2005, Entergy Operations requested an exemption from the requirements of 10 CFR 72.212(a)(2) and 10 CFR 72.214, specifically, exemption from complying with Appendix B, Section 2.1, of the HI-STORM 100 Cask System CoC (1014), Fuel Specifications and Loading Conditions. The NRC action would also include granting exemption from the requirements of 10 CFR 72.212(b)(2)(I) and 72.212(b)(7). Approval of the exemption request would allow storage of uncanned damaged SNF assemblies in a HI-STORM 100, Amendment 1 design, MPC-32. Damaged SNF assemblies may be stored in an HI-STORM 100, Amendment 2 design, MPC-32 when properly canned. Entergy Operations has identified five previously loaded intact fuel assemblies that have been reclassified as damaged SNF assemblies. A damaged SNF assembly is defined in the HI-STORM 100, Amendment 1 CoC in part as one with greater than pinhole leak or hairline cracks. Each of the five SNF assemblies classified as damaged contain one interior rod characterized as defective. In accordance with Amendment 1 to CoC 1014 granted to Holtec for the HI-STORM 100 cask system, and as codified in 10 CFR 72.214, the MPC-32 is not permitted to store damaged fuel assemblies. ANO as a general licensee, is authorized by the NRC to use spent fuel storage casks approved under 10 CFR Part 72, Subpart K. For the NRC to permit Entergy Operations to continue to store the five uncanned damaged SNF assemblies in four HI-STORM 100, Amendment 1 design, MPC-32's, the NRC, must grant Entergy Operations an exemption from the general license conditions defined in 10 CFR 72.212. The regulations in 10 CFR 72.212 state that the general license for storage of SNF at power reactor sites is limited to storage of SNF in casks approved under the provisions in 10 CFR Part 72. By exempting Entergy Operations from 10 CFR 72.214 and 72.212(a)(2), 72.212(b)(2)(I), and 72.212(b)(7), Entergy Operations will be authorized to use its general license to store uncanned damaged SNF assemblies in the HI-STORM 100, Amendment 1 design, MPC-32. The proposed action before the Commission is whether to grant the exemption under 10 CFR 72.7. The ISFSI is located 6 miles west-northwest of Russellville, Arkansas, on the ANO Power Plant site. The ANO ISFSI is an existing facility constructed for interim dry storage of spent ANO nuclear fuel. II. Need for the Proposed Action Five uncanned damaged SNF assemblies are currently loaded into four HI-STORM 100, Amendment 1 design, MPC-32's stored at the ANO ISFSI. Unloading of the damaged SNF assemblies would subject personnel to a significant unnecessary dose, generate additional contaminated waste, increase the risk of a possible fuel handling accident, and increase the risk of a heavy load handling accident. Discharge of the damaged SNF assemblies from storage in the MPCs would result in inadequate storage capacity in the ANO Unit 2 Spent Fuel Pool. If the damaged SNF assemblies are discharged into the spent fuel pool, storage of new fuel and the restoration of normal full core offload capability prior to and after the next refueling outage would be challenged. Recovery of spent fuel pool space could be significantly hindered due to double handling of ANO Unit 2 fuel in addition to material and scheduling conflicts with ANO Unit 1 activities to the extent that ANO Unit 2 core offloads could be jeopardized. III. Environmental Impacts of the Proposed Action The potential environmental impact of using the HI-STORM 100 system was initially presented in the Environmental Assessment for the final rule to add the HI-STORM 100 system to the list of approved spent fuel storage casks in 10 CFR 72.214 (65 FR 25241; May 1, 2000). Furthermore, each general licensee must assess the environmental impacts of the specific ISFSI in accordance with the requirements of 10 CFR 72.212(b)(2)(iii). This section requires the general licensee to perform written evaluations to demonstrate compliance with the environmental requirements of 10 CFR 72.104, “Criteria for radioactive materials in effluents and direct radiation from an ISFSI or MRS [Monitored Retrievable Storage Installation].” The HI-STORM 100 system is designed to mitigate the effects of design basis accidents that could occur during storage. Design basis accidents account for human-induced events and the most severe natural phenomena reported for the site and surrounding area. Postulated accidents analyzed for an ISFSI include tornado winds and tornado generated missiles, design basis earthquake, design basis flood, accidental cask drop, lightning effects, fire, explosions, and other incidents. Considering the specific design requirements for each accident condition, the design of the HI-STORM 100, Amendment 1, cask system using an MPC-32 basket design, would prevent loss of containment, shielding, and criticality control. The loading of damaged SNF has no impact on the structural aspects of the containment boundary. The HI-STORM 100, Amendment 1 design permits storage of damaged SNF assemblies in the MPC-24 and MPC 68 which utilize the same outer containment boundary as the MPC-32. Dose surveys performed prior to placing each cask in service, including those MPC-32s containing the damaged SNF assemblies, demonstrated that each cask satisfied the dose requirements defined in the HI-STORM 100 Amendment 1 CoC. Any relocation of the damaged fuel rods, in the fuel assembly, within the MPC has a negligible effect on the k <sup>eff</sup> (criticality control) of the system predominantly due to the fact that there are no more than two individual damaged fuel rods per MPC. Without the loss of either containment, shielding, or criticality control, the risk to public health and safety from the continued storage of five damaged SNF assemblies in four HI-STORM 100, Amendment 1 design, MPC-32s, is not compromised. By permitting the continued storage of five uncanned damaged SNF assemblies using HI-STORM 100 system, Amendment 1 design, MPC-32s, there will be no additional occupational exposure due to unloading activities, and offsite dose rates will remain well within the 10 CFR Part 20 limits. Therefore, the NRC staff has determined that an acceptable safety margin is maintained and that there are no significant environmental impacts as a result of continuing to store five damaged SNF assemblies in four HI-STORM 100, Amendment 1, MPC-32s at the ANO ISFSI. IV. Alternatives to the Proposed Action The staff evaluated the alternative to the proposed action to deny approval of the exemption. Denial of the exemption request would result in unloading of the damaged SNF assemblies subjecting personnel to unnecessary dose, the generation of additional contaminated waste, an increase in the risk of a possible fuel handling accident, an increase in the risk of a heavy load handling accident, and result in inadequate storage capacity in the ANO Unit 2 Spent Fuel Pool jeopardizing the ability to fully offload the ANO Unit 2 core. V. Agencies and Persons Consulted On July 11, 2005, Bernard Bevill from the Radiation Control Work Unit, Arkansas Department of Health, was contacted about the EA for the proposed action and had no concerns. 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 EA, the Commission finds that the proposed action of granting an exemption from 10 CFR 72.212(a)(2), 72.212(b)(2)(I), 72.212(b)(7), and 72.214 so that Entergy Operations may continue to store uncanned damaged SNF assemblies in a Holtec HI-STORM 100, Amendment 1 design, MPC-32, at the ANO, Units 1 and 2 ISFSI, will not significantly impact the quality of the human environment. Further Information In accordance with 10 CFR 2.390 of NRC's “Rules of Practice,” final NRC records and documents regarding this proposed action, including the exemption request dated March 21, 2005, are publically available in the records component of NRC's Agencywide Documents Access and Management System (ADAMS). These documents may be inspected at NRC's Public Electronic Reading Room at *http://www.nrc.gov/reading-rm/adams.html.* These documents may also be viewed electronically on the public computers located at the NRC's Public Document Room (PDR), O1F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. 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 or

(301)415-4737, or by e-mail to *pdr@nrc.gov.* Dated at Rockville, Maryland, this 20th day of July 2005. For the Nuclear Regulatory Commission. Christopher M. Regan, Senior Project Manager, Spent Fuel Project Office, Office of Nuclear Material Safety and Safeguards. [FR Doc. E5-3993 Filed 7-26-05; 8:45 am] BILLING CODE 7590-01-P OVERSEAS PRIVATE INVESTMENT CORPORATION July 28, 2005, Board of Directors Meeting; Correction AGENCY: Overseas Private Investment Corporation, 1100 New York Avenue, NW., Washington, DC. ACTION: Correction to meeting notice published in Vol. 70, No. 137/Tuesday, July 19, 2005, page 41449. SUMMARY: OPIC's Board or Directors meeting previously scheduled for 10 a.m. on Thursday, July 28, 2005, has been moved to 9:30 a.m. *New Time and Date:* Thursday, July 28, 2005, 9:30 a.m. (open portion); 9:45 a.m. (closed portion). *Contact Person for Information:* Information on the meeting may be obtained from Connie M. Downs at

(202)336-8438. Dated: July 22, 2005. Connie M. Downs, Corporate Secretary, Overseas Private Investment Corporation [FR Doc. 05-14922 Filed 7-25-05; 10:30 am]

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