Notices. NUCLEAR REGULATORY COMMISSION

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BILLING CODE 4510-24-P NUCLEAR REGULATORY COMMISSION [Docket No. 50-368] Entergy Operations, Incorporated; 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, NRC) is considering issuance of an amendment to Facility Operating License No. NFP-6, issued to Entergy Operations Incorporated (the licensee), for operation of Arkansas Nuclear One Unit 2 (ANO-2), located in Pope county.

The proposed amendment would define spent fuel loading restrictions for the Holtec International HI-STORM 100 Cask System Multi-Purpose Canister (MPC)-32. The licensee will be removing spent fuel from the spent fuel pool and placing it in dry storage as early as September 2005. This activity will restore the full-core offload capability at ANO-2. The licensee believed that the calculation that considered the requirements of 10 CFR 50.68 for loading/unloading an MPC-32 met the criteria of 10 CFR 50.59 and 10 CFR 50.36, and did not require NRC review and approval.

However, based on Regulatory Information Summary

(RIS)2005-05, “Regulatory Issues Regarding Criticality Analyses for Spent Fuel Pools and Independent Spent Fuel Storage Installations,” the licensee submitted a pre-application letter to the NRC outlining the plans to submit a non-exigent technical specification

(TS)change and justification for continued operations without prior NRC approval based on guidance contained in Administrative Letter 98-10, “Dispositioning of Technical Specifications that are Insufficient to Assure Plant Safety,” and Generic Letter 91-18, “Information to Licensees Regarding Two NRC Inspection Manual Sections on Resolution of Degraded and Nonconforming Conditions and on Operabiltiy.” In a teleconference between the licensee and the NRC staff held on July 19, 2005, the NRC stated that it did not believe ANO-2 was in compliance with 10 CFR 50.68 and, therefore, the proposed change required NRC approval prior to proceeding with cask loading activities. 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. Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under exigent circumstances, the NRC staff must determine that the amendment request involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this means that 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: 1. Does the proposed change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The fuel handling accidents described below can be postulated to increase reactivity. However, for these accident conditions, the double contingency principle of ANS N16.1-1975 is applied. This states that it is unnecessary to assume two unlikely, independent, concurrent events to ensure protection against a criticality accident. Thus, for accident conditions, the presence of soluble boron in the SFP [spent fuel pool] water can be assumed as a realistic initial condition since its absence would be a second unlikely event. Loading/unloading a storage cask in the SFP does not affect the previously evaluated fuel handling accidents ( *i.e.* , criticality effects) in the SFP. The ANO-2 TS for SFP boron concentration ensures subcritical conditions in the SFP during fuel movement activities, whether within the SFP racks or to a storage cask during normal and accident conditions. The cask configuration for the storage cask (MPC-32) is sufficiently similar to spent fuel racks in the SFP as to not induce new or different spent fuel assembly damage in the unlikely event of the occurrence of a fuel handling accident during storage cask loading/unloading activities. The fuel handling accident includes four drop scenarios (fuel drop horizontally on a cask, fuel drop on a fuel assembly, fuel drop next to a cask, and a fuel drop on the cask basket). The same equipment and procedural controls for controlling fuel within the SFP are utilized when loading/unloading a storage cask. In addition, the postulated fuel handling accidents associated with loading/unloading a storage cask are bounded by current ANO-2 TS SFP requirements for minimum boron concentration. Loading/unloading a storage cask will have no impact on the boron dilution event probability. The same controls for prohibiting a dilution event during spent fuel movement activities in the SFP are in use when loading/unloading fuel in a cask located in the cask pit. Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The storage casks have the same basic design and control of a SFP rack. The cask cell walls are thicker than the SFP rack walls; the outside wall on the cask is thicker than the SFP racks and the space for mishandling is tighter than around the racks. When the cask loading pit gate is open and the Technical Specifications are applicable, the pit is in direct communications with the spent fuel pool. Boron concentrations and decay heat removal for fuel in the cask loading pit is controlled in the same manner as it is for fuel in the spent fuel pool proper. An accident analysis for the MPC-32 was performed assuming the same SFP rack accidents that are discussed in the ANO-2 SAR [safety analysis report]. The ANO-2 TS boron concentration assures that a subcritical margin is maintained during any postulated accident condition ( *i.e.* , k eff [effective neutron multiplication coefficient] is less than or equal to 0.95). 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 reduction in a margin of safety? Response: No. The ANO-2 TSs require for criticality concerns in the SFP that k eff remain less than or equal to 0.95. For the MPC-32, the criticality analysis demonstrated that when the ANO-2 TS for SFP boron concentration is met, a loading restriction is required to ensure k eff remains less than or equal to 0.95. The proposed change to the ANO-2 TS will ensure the criticality margin is maintained. Therefore, 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 14 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 the 14-day notice period. However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example, in derating or shutdown of the facility, the Commission may issue the license amendment before the expiration of the 14-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the **Federal Register** a notice of 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, 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 and Issuance of Orders” 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 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 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 requestor's/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/requestor is aware and on which the petitioner/requestor intends to rely to establish those facts or expert opinion. The petitioner/requestor must provide 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. 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;

(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* . A copy of the request for hearing and petition for leave to intervene should also be sent to Nicholas S. Reynolds, Esquire, Winston and Strawn, 1700 K Street, NW., Washington, DC 20006-3817, attorney for the licensee. For further details with respect to this action, see the application for amendment dated July 21, 2005, which 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. Publicly available records will be accessible electronically from the ADAMS Public Electronic Reading Room on the Internet at the NRC Web site *http://www.nrc.gov/reading-rm.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 in Rockville, Maryland, this 9th day of August 2005. For the Nuclear Regulatory Commission. Drew G. Holland, Project Manager, Section 1, Project Directorate IV, Division of Licensing Project Management, Office of Nuclear Reactor Regulation. [FR Doc. E5-4418 Filed 8-15-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 and 50-301] Nuclear Management Company, LLC; 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-24 and DPR-27 issued to Nuclear Management Company, LLC (the licensee), for operation of the Point Beach Nuclear Plant (PBNP), Units 1 and 2, located in the Town of Two Creeks, Manitowoc County, Wisconsin. The proposed amendments would revise the licensing basis as described in the Point Beach Nuclear Plant Final Safety Analysis Report to incorporate the proposed Unit 1 reactor vessel head

(RVH)drop analysis and the revised Unit 2 RVH drop analysis. 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 requests involve 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 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

(LOCA)under shutdown conditions. A RVH drop is of sufficiently low probability such that, for Unit 1, the probability of a LOCA is not significantly increased over the current licensing basis large break LOCA. For Unit 2, the probability is unchanged from the previously approved RVH drop analysis. For Unit 1, supplemental administrative controls have been established to assure continued availability of multiple independent sources of water to provide core cooling and makeup water well in excess of the postulated LOCA. Containment closure will also be established during this evolution. No pressurization of the reactor coolant system will occur as a result of this postulated event. For Unit 2, the previously approved administrative controls have been revised, consistent with those submitted for Unit 1 herein, to provide additional makeup water capacity. The calculated radiological consequences of the postulated RVH drop are within those calculated for the current licensing basis large break LOCA. Therefore, the consequences of a LOCA are not increased. The proposed change is consistent with safety analysis assumptions and resultant consequences. All Technical Specifications are satisfied and required equipment is operable. Therefore, this change would not significantly increase the probability of occurrence or consequences of any accident previously evaluated. 2. Would the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. For Unit 1, the proposed change incorporates the revised heavy load analysis into the PBNP FSAR. This analysis involves the postulated drop of the RVH over a reactor vessel containing fuel assemblies. Assuming that the BMI tubes are severed as a result of displacement of the reactor vessel, a decrease in reactor coolant inventory will occur. Thus, a RVH drop can be postulated as an initiator of a LOCA under shutdown conditions. Adequate core cooling and makeup water remains available from core cooling water systems. Maintaining core cooling and makeup and closing containment assures that the drop of a RVH is bounded by the existing licensing basis analysis for a LOCA. The drop of a RVH was previously evaluated by the NRC for Unit 2 in a safety evaluation dated June 24, 2005. Therefore, the proposed changes would not create the possibility of a new or different kind of accident from any previously evaluated. 3. Would the proposed amendment result in a significant reduction in a margin of safety? Response: No. For Unit 1, the proposed change incorporates the revised heavy load analysis into the PBNP FSAR. This analysis involves the postulated drop of the RVH over a reactor vessel containing fuel assemblies. Assuming that the BMI tubes are severed as a result of displacement of the reactor vessel, a decrease in reactor coolant inventory will occur. Thus, a RVH drop can be postulated as an initiator of a LOCA under shutdown conditions. The frequency and consequences of a RVH drop are comparable to or within those of the current licensing basis large break LOCA. The proposed change does not alter any safety limits, limiting safety system settings, or limiting conditions for operation as defined in the Technical Specifications. The drop of a RVH was previously evaluated by the NRC for Unit 2 in a safety evaluation dated June 24, 2005. Therefore, the proposed amendment does not result in 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 amendments until the expiration of 60 days after the date of publication of this notice. The Commission may issue the license amendments before expiration of the 60-day period provided that its final determination is that the amendments involve no significant hazards consideration. In addition, the Commission may issue the amendments 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 amendments 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 requestor's/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: Rulemaking 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 the Jonathan Rogoff, Esquire, Vice President, Counsel & Secretary, Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016, attorney for the licensee. For further details with respect to this action, see the application for amendments dated July 24, 2005, which is available for public inspection at the Commission's PDR, located at One White Flint North, File Public 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 10th day of August 2005. For the Nuclear Regulatory Commission. Harold K. Chernoff, Senior Project Manager, Section 1, Project Directorate III, Division of Licensing Project Management, Office of Nuclear Reactor Regulation. [FR Doc. E5-4419 Filed 8-15-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION Sunshine Federal Register Notice Agency Holding The Meetings: Nuclear Regulatory Commission. Date: Weeks of August 15, 22, 29, and September 5, 12, 19, 2005. Place: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. Status: Public and closed. Matters to be considered: Week of August 15, 2005 Tuesday, August 16, 2005. 10 a.m. Meeting with Organization of Agreement States

(OAS)and the Conference of Radiation Control Program Directors CRCPD) (Public Meeting) (Contact: Shawn Smith, 301-415-2620). This meeting will be Web cast live at the Web address— *http://www.nrc.gov* . 1 p.m. Discussion of Security Issues (Closed—Ex. 3 & 9). Week of August 22, 2005—Tentative There are no meetings scheduled for the week of August 22, 2005. Week of August 29, 2005—Tentative There are no meetings scheduled for the week of August 29, 2005. Week of September 5, 2005—Tentative Wednesday, September 7, 2005. 9 a.m. Discussion of Security Issues (Closed—Ex. 1). 1:30 p.m. Discussion of Security Issues (Closed—Ex. 3). Week of September 12, 2005—Tentative There are no meetings scheduled for the week of September 12, 2005. Week of September 19, 2005—Tentative There are no meetings scheduled for the week of September 19, 2005. *The schedule for Commission meetings is subject to change on short notice. To verify the status of meetings call (recording)—(301) 415-1292. Contact person for more information: Michelle Schroll,

(301)415-1662. The NRC Commission Meeting Schedule can be found on the Internet at: *http://www.nrc.gov/what-we-do/policy-making/schedule.html* . The NRC provides reasonable accommodation to individuals with disabilities where appropriate. If you need a reasonable accommodation to participate in these public meetings, or need this meeting notice or the transcript or other information from the public meetings in another format ( *e.g.* , braille, large print), please notify the NRC's Disability Program Coordinator, August Spector, at 301-415-7080, TDD: 301-415-2100, or by e-mail at *aks@nrc.gov* . Determinations on requests for reasonable accommodation will be made on a case-by-case basis. This notice is distributed by mail to several hundred subscribers; if you no longer wish to receive it, or would like to be added to the distribution, please contact the Office of the Secretary, Washington, DC 20555 (301-415-1969). In addition, distribution of this meeting notice over the Internet system is available. If you are interested in receiving this Commission meeting schedule electronically, please send an electronic message to *dkw@nrc.gov* . Dated: August 11, 2005. R. Michelle Schroll, Office of the Secretary. [FR Doc. 05-16256 Filed 8-12-05; 10:22 am]

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