Notices. Notice of request for exemption from the requirements of 10 CFR 72

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BILLING CODE 7555-01-M NUCLEAR REGULATORY COMMISSION [Docket No 72-13] Entergy Operations, Incorporated; Notice of Docketing of Request for Exemption for Arkansas Nuclear One, Unit 1 and Unit 2 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of request for exemption from the requirements of 10 CFR 72.212(a)(2) and 10 CFR 72.214. 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: I. Introduction The U.S. Nuclear Regulatory Commission (NRC or Commission) is considering a request dated May 23, 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, Unit 1 (ANO-1) and Unit 2 (ANO-2), facility located 6 miles west-northwest of Russellville, Arkansas. If granted, the exemption will authorize the applicant to load spent nuclear fuel in accordance with proposed Amendment 2 to Certificate of Compliance

(CoC)1014 granted to Holtec International (Holtec) for the HI-STORM 100 system. This request was docketed under 10 CFR Part 72; the Independent Spent Fuel Storage Installation Docket No. is 72-13. An NRC administrative review, documented in a letter to Entergy Operations dated June 2, 2005, found that the application contains sufficient information for the NRC staff to begin its technical review. Prior to issuance of the requested exemption, the Commission will have made the findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations. These findings will be documented in a Safety Evaluation Report. The issuance of the exemption will not be approved until the NRC has reviewed the application and has concluded that granting of the request will not be inimical to the common defense and security and will not constitute an unreasonable risk to the health and safety of the public. The NRC will complete an environmental assessment, in accordance with 10 CFR part 51. This action will be the subject of a subsequent notice in the **Federal Register** . II. 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 May 23, 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 2nd day of June 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. E5-2917 Filed 6-7-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 50-255] Nuclear Management Company, LLC, Palisades Nuclear Plant; Notice of Acceptance for Docketing of the Application and Notice of Opportunity for Hearing Regarding Renewal of Facility Operating License No. DPR-20 for an Additional 20-Year Period The U.S. Nuclear Regulatory Commission (NRC or the Commission) is considering application for the renewal of Operating License No. DPR-20, which authorizes the Nuclear Management Company, LLC, to operate the Palisades Nuclear Plant at 2530 megawatts thermal. The renewed license would authorize the applicant to operate the Palisades Nuclear Plant, for an additional 20 years beyond the period specified in the current license. The current Operating License for the Palisades Nuclear Plant expires on March 24, 2011. The Commission's staff has received an application dated March 22, 2005 and a supplement dated May 5, 2005, from Nuclear Management Company, LLC, pursuant to 10 CFR Part 54, to renew the operating license DPR-20 for the Palisades Nuclear Plant. A Notice of Receipt and Availability of the license renewal application, “Nuclear Management Company, LLC; Palisades Nuclear Plant; Notice of Receipt and Availability of Application for Renewal Facility Operating License No. DPR-20 for an Additional 20-Year Period,” was published in the **Federal Register** on April 12, 2005. The Commission's staff has determined that Nuclear Management Company, LLC has submitted sufficient information in accordance with 10 CFR 54.19, 54.21, 54.22, 54.23, and 51.53(c) that is acceptable for docketing. The current Docket No. 50-255 for Operating License No. DPR-20 will be retained. The docketing of the renewal application and supplement 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 licenses 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 requestor/petitioner 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 licenses. 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's (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 at 1-800-397-4209, or by email at *pdr@nrc.gov.* If a request for a hearing or a 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 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. In the event that no request for a hearing or 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 licenses 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 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. Each contention shall be given a separate numeric or alpha designation within one of the following groups and all like subject-matters shall be grouped together: 1. Technical—primarily concerns issues relating to technical and/or health and safety matters discussed or referenced in the Palisades Nuclear Plant, safety analysis for the application (including issues related to emergency planning and physical security to the extent that such matters are discussed or referenced in the application). 2. Environmental—primarily concerns issues relating to matters discussed or referenced in the Environmental Report for the license renewal application 3. Miscellaneous—does not fall into one of the categories outlined above. 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, including 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)Email 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 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 licensee. Jonathan Rogoff, Esquire, Vice President, Counsel & Secretary, Nuclear Management Company, LLC, 700 First Street, Hudson, WI 54016. Nontimely 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 and supplement to renew the operating licenses for Palisades Nuclear Plant, 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 numbers ML050940434 and ML051300128. 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 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 and supplement are also available to local residents near the Palisades Nuclear Plant, at the South Haven Memorial Library, 314 Broadway, South Haven, MI 49090. Dated at Rockville, Maryland, this 2nd day of June, 2005. For the Nuclear Regulatory Commission. Samson S. Lee, Acting Program Director, License Renewal and Environmental Impacts Program, Division of Regulatory Improvement Programs, Office of Nuclear Reactor Regulation. [FR Doc. E5-2914 Filed 6-7-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-266 and 50-301] Nuclear Management Company, LLC, Point Beach Nuclear Plant, Units 1 and 2; Exemption 1.0 Background Nuclear Management Company, LLC (NMC, the licensee), is the holder of Facility Operating License Nos. DPR-24 and DPR-27 which authorizes operation of the Point Beach Nuclear Plant, Units 1 and 2. The licenses provide, among other things, that the facility is subject to all rules, regulations, and orders of the U.S. Nuclear Regulatory Commission (NRC, the Commission) now or hereafter in effect. The facility consists of two pressurized-water reactors

(PWR)located in Manitowoc County, Wisconsin. 2.0 Request/Action Title 10 of the Code of Federal Regulations (10 CFR) Part 50, Appendix R, “Fire Protection Program for Nuclear Power Facilities Operating Prior to January 1, 1979,” established fire protection

(FP)requirements to satisfy 10 CFR 50, appendix A, General Design Criterion 3, “Fire Protection.” Appendix R, Section III.G.1.a of 10 CFR Part 50 requires: “one train of systems necessary to achieve and maintain hot shutdown from either the control room or emergency control station(s) is free of fire damage * * *” By letter dated March 5, 2004, the licensee requested a permanent exemption from the requirements of 10 CFR Part 50, appendix R, Section III.G.1.a for a repair consisting of powering a dedicated air compressor from one of two pre-planned 480 volt power sources using pre-staged power cords and connecting the air compressor to nitrogen bottle manifolds on one or both reactor units using a pre-staged pneumatic hose with quick connect fittings. The licensee stated: The existing Safe Shutdown Analysis

(SSA)for Point Beach credits a hard-piped nitrogen bottle bank to provide the first several hours of charging pump control air during hot shutdown. However, if the normal source of instrument air is not restored prior to depletion of this bottle bank, a dedicated air compressor is available to provide continued support for long term hot shutdown (and/or subsequent transition to cold shutdown) operation. This air compressor must be connected to a suitable power supply by means of electrical cables and to the charging pump backup control air manifolds by portable hoses. 3.0 Discussion Pursuant to 10 CFR 50.12, the Commission may, upon application by any interested person or upon its own initiative, grant exemptions from the requirements of 10 CFR Part 50 when

(1)the exemptions are authorized by law, will not present an undue risk to public health or safety, and are consistent with the common defense and security; and

(2)when special circumstances are present. Section 50.12(a)(2)(ii) of 10 CFR states that special circumstances are present whenever “application of the regulation in the particular circumstances would not serve the underlying purpose of the rule or is not necessary to achieve the underlying purpose of the rule. * * *” 10 CFR Part 50, Appendix R, Section III.G.1.a requires that, “one train of systems necessary to achieve and maintain hot shutdown conditions from either the control room or emergency control station(s) is free of fire damage.” Appendix R, Section III.L.1, of 10 CFR Part 50 requires that an alternative or dedicated shutdown capability shall be able to, among other things, “(c) achieve and maintain hot standby conditions for a PWR; and

(d)achieve cold shutdown conditions within 72 hours.” NRC Inspection Report 50-266/2003-007; 50-301/2003-007, dated February 4, 2004, documents a Non-Cited Violation of Appendix R, Section III.L.1.c, in that NMC, “failed to ensure, without the need for 'hot standby repairs,' adequate control air to the speed controllers for the charging pumps during a postulated fire requiring an alternative shutdown method.” The installed backup nitrogen gas bottle bank (for the charging pump speed controllers) meets the requirements of the regulation, with the exception that it is of limited capacity. This means that the hot shutdown conditions could not be maintained indefinitely while relying only on the installed bottle bank. However, the 8 to 14 hour capacity of the bottle banks is ample time to extinguish the fire, achieve stable plant conditions in hot shutdown, augment staff with personnel from the emergency response organization, and connect dedicated power cabling and hoses to the dedicated compressor using the furnished plugs and quick connect fittings ( *i.e.,* no tools required). Because the bottle banks, hoses, cables, and compressor are all located in areas that would not be affected by the fires of concern, none would be damaged. The installed backup bottle banks are normally isolated from the charging pump pneumatic controls by the bottle stop-cocks, a manual valve on the bottle manifold, and an in-line manual isolation valve. These valves must be opened to bring the backup nitrogen on line. In contrast, the (staged) dedicated air compressor must be connected to its power supply by retrieving the staged cable and hose(s) from their storage locations in the same fire area (Turbine Hall), laying them out from the compressor to the selected power supply and to the affected unit's backup bottle bank manifold, and then connecting the cable and hoses using the installed plugs and quick connect fittings before starting the compressor. Although this activity could be considered a “hot standby repair,” connection of these undamaged components to support continued hot shutdown conditions within 8 hours of the initiating event is reasonably achievable. This can be performed without invoking extraordinary action and without perturbing the stable plant conditions. Therefore, strict application of the interpretation proscribing any hot standby repair is not necessary to achieve and maintain hot shutdown conditions while relying only on the operating shift personnel, without undue encumbrances, and without having to resort to significant time consuming “repairs.” The NRC staff concludes that application of Section III.G.1.a under these circumstances is not necessary to achieve the underlying purpose of the rule. The NRC staff examined the licensee's rationale to support the exemption request and concluded that sufficient time (8 hours) is available to make the necessary connections to operate the backup air compressor. The NRC staff is satisfied that on-site and augmented response resources will be available to complete the repair. The appropriate equipment for this evolution is pre-staged. The NRC staff considered the location of the air compressor, the transformer, the pre-staging locations and routing of the electrical cables, and the pre-staging locations and routing of the pneumatic hoses. Equipment is pre-staged such that no single fire will affect permanent plant equipment and the repair equipment. The repair steps are feasible and reliable. The actions requested, hooking up power cables and connecting pneumatic fittings for the air compressor, are repairs as commonly implemented by appendix R [but would not meet the requirements of] Section III.G.1.a (achieving and maintaining hot standby). The NRC staff agrees, therefore, that an exemption is appropriate to meet the underlying purpose of Section III.G.1.a, and that the 10 CFR 50.12.(a)(2)(ii) criterion applicable to this request. 4.0 Conclusion Accordingly, the Commission has determined that, pursuant to 10 CFR 50.12(a), the exemption is authorized by law, will not present an undue risk to the public health and safety, and is consistent with the common defense and security. Also, special circumstances are present. Therefore, the Commission hereby grants NMC an exemption from the requirements of 10 CFR Part 50, appendix R, Part III.G.1.a, for Point Beach Nuclear Plant, Units 1 and 2. Pursuant to 10 CFR 51.32, the Commission has determined that the granting of this exemption will not have a significant effect on the quality of the human environment (70 FR 30819). This exemption is effective upon issuance. Dated at Rockville, Maryland, this 2nd day of June, 2005. For the Nuclear Regulatory Commission. Ledyard B. Marsh, Director, Division of Licensing Project Management, Office of Nuclear Reactor Regulation. [FR Doc. E5-2915 Filed 6-7-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 72-42] Southern Nuclear Operating Company, Incorporated; Notice of Docketing of Request for Exemption for the Joseph M. Farley Nuclear Plant, Unit 1 and Unit 2 AGENCY: Nuclear Regulatory Commission. ACTION: Notice of request for exemption from the requirements of 10 CFR 72.212(a)(2) and 10 CFR 72.214. 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: I. Introduction The U.S. Nuclear Regulatory Commission (NRC or Commission) is considering a request dated May 20, 2005, from Southern Nuclear Operating Company, Inc. (applicant or SNC) 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 Joseph M. Farley Nuclear Plant (FNP), Unit 1 and Unit 2, facility located in Houston County, Alabama. If granted, the exemption will authorize the applicant to load spent nuclear fuel in accordance with proposed Amendment 2 to Certificate of Compliance

(CoC)1014 granted to Holtec International (Holtec) for the HI-STORM 100 system. This request was docketed under 10 CFR Part 72; the Independent Spent Fuel Storage Installation Docket No. is 72-42. An NRC administrative review, documented in a letter to SNC dated June 2, 2005, found that the application contains sufficient information for the NRC staff to begin its technical review. Prior to issuance of the requested exemption, the Commission will have made the findings required by the Atomic Energy Act of 1954, as amended (the Act), and the Commission's regulations. These findings will be documented in a Safety Evaluation Report. The issuance of the exemption will not be approved until the NRC has reviewed the application and has concluded that granting of the request will not be inimical to the common defense and security and will not constitute an unreasonable risk to the health and safety of the public. The NRC will complete an environmental assessment, in accordance with 10 CFR part 51. This action will be the subject of a subsequent notice in the **Federal Register** . II. 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 May 20, 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 2nd day of June, 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. E5-2918 Filed 6-7-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 50-305; License No. DPR-43] In the Matter of Wisconsin Public Service Corporation, Wisconsin Power and Light Company, and Nuclear Management Company, LLC (Kewaunee Nuclear Power Plant, Unit No. 1); Order Extending the Effectiveness of the Approval of the Transfer of License and Conforming Amendment Wisconsin Public Service Corporation (WPSC), Wisconsin Power and Light Company (WPL), and Nuclear Management Company, LLC

(NMC)(the licensees) are the holders of Facility Operating License No. DPR-43, which authorizes operation of Kewaunee Nuclear Power Plant, Unit No. 1 (Kewaunee or the facility). The facility is located at the licensees' site in Kewaunee County, Wisconsin. The license authorizes WPSC and WPL to possess, and NMC to use and operate, Kewaunee. By order dated June 10, 2004, the Commission approved the transfer of the license for Kewaunee to Dominion Energy Kewaunee, Inc. (Dominion Energy Kewaunee). By its terms, the order of June 10, 2004, becomes null and void if the license transfer is not completed by June 30, 2005, unless upon application and for good cause shown, the Commission extends the effectiveness of the approval. By letter dated May 4, 2005, NMC, on behalf of itself, WPSC, and WPL, submitted a request to extend the effectiveness of the order of June 10, 2004, until December 31, 2005. According to the letter, Kewaunee is currently in an extended unit shutdown to address certain recently identified design issues. Based on the current asset sales agreement between the owners and Dominion Energy Kewaunee, the license transfer will not occur until the unit has been returned to full power operation. The licensee's present schedule for addressing the plant design issues, returning the unit to full power operation, and completing the license transfer shows that all of these items will be done before June 30, 2005. However, Dominion Energy Kewaunee and NMC consider it prudent to request an extension of the order approving the license transfer if unforeseen circumstances make an extension necessary. Therefore, NMC requests an extension of the order until December 31, 2005, to permit completion of the Kewaunee license transfer. In its May 4, 2005, letter, NMC also stated that no conditions under which the NRC order was granted have been significantly changed or detrimentally affected since the order was issued. The NRC staff has considered the licensee's May 4, 2005, request and has determined that the licensee has shown good cause for extending the effectiveness of the order of June 10, 2004, as requested. Accordingly, pursuant to Sections 161b, 161i, and 184 of the Atomic Energy Act of 1954, as amended, 42 U.S.C. 2201(b), 2201(i), and 2234, and 10 CFR 50.80, it is hereby ordered that the effectiveness of the herein described order of June 10, 2004, is extended such that if the subject license transfer from NMC, WPSC, and WPL to Dominion Energy Kewaunee referenced above is not completed by December 31, 2005, the order of June 10, 2004, shall become null and void, unless upon application and for good cause shown, the Commission further extends the effectiveness of the order. This Order is effective upon issuance. For further details with respect to this action, see the submittal dated May 4, 2005, which is available for public inspection at the Commission's Public Document Room, located at One White Flint North, 11555 Rockville Pike (first floor), Rockville, Maryland, and is accessible electronically through the ADAMS Public Electronic Reading Room link at the NRC Web site ( *http://www.nrc.gov* ). Dated at Rockville, Maryland, this 1st day of June, 2005. For The Nuclear Regulatory Commission. J. Dyer, Director, Office of Nuclear Reactor Regulation. [FR Doc. E5-2916 Filed 6-7-05; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION Notice of Availability of Interim Staff Guidance Documents for Fuel Cycle Facilities AGENCY: Nuclear Regulatory Commission. ACTION: Notice of availability. FOR FURTHER INFORMATION CONTACT: Wilkins Smith, Project Manager, Technical Support Group, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20005-0001. Telephone:

(301)415-5788; fax number:

(301)415-5370; e-mail: *wrs@nrc.gov.* SUPPLEMENTARY INFORMATION: I. Introduction The Nuclear Regulatory Commission

(NRC)is preparing and issuing Interim Staff Guidance

(ISG)documents for fuel cycle facilities. These ISG documents provide clarifying guidance to the NRC staff when reviewing licensee integrated safety analyses, license applications or amendment requests or other related licensing activities for fuel cycle facilities under Subpart H of 10 CFR Part 70. The NRC is soliciting public comments on one ISG Draft document (ISG-08) which will be considered in the final version or subsequent revision. II. Summary The purpose of this notice is to provide the public an opportunity to review and comment on the Interim Staff Guidance document for fuel cycle facilities. Draft Interim Staff Guidance-08, Version 0, provides guidance to NRC staff relative to evaluation of natural phenomena hazards in the context of a review of a license application or amendment request or other licensee submittal under 10 CFR Part 70, Subpart H. III. Further Information Documents related to this action are available electronically at the NRC's Electronic Reading Room at *http://www.nrc.gov/reading-rm/adams.html.* From this site, you can access the NRC's Agencywide Document Access and Management System (ADAMS), which provides text and image files of NRC's public documents. The ADAMS accession number for the document related to this notice is provided in the following table. If you do not have access to ADAMS or if there are problems in accessing the document located in ADAMS, contact the NRC Public Document Room

(PDR)Reference staff at 1-800-397-4209, 301-415-4737, or by e-mail to *pdr@nrc.gov.* Interim Staff Guidance ADAMS Accession No. Interim Staff Guidance-08, Version 0 ML051470304 This document may also be viewed electronically on the public computers located at the NRC's PDR, O 1 F21, One White Flint North, 11555 Rockville Pike, Rockville, MD 20852. The PDR reproduction contractor will copy documents for a fee. Comments and questions on ISG-08 should be directed to the NRC contact listed below by July 8, 2005. Comments received after this date will be considered if it is practical to do so, but assurance of consideration cannot be given to comments received after this date. Comments should be directed to Wilkins Smith, Project Manager, Technical Support Group, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20005-0001. Comments can also be submitted by telephone, fax, or e-mail which are as follows: Telephone:

(301)415-5788; fax number:

(301)415-5370; e-mail: *wrs@nrc.gov.* Dated at Rockville, Maryland this 1st day of June, 2005. For the Nuclear Regulatory Commission. Melanie A. Galloway, Chief, Technical Support Group, Division of Fuel Cycle Safety and Safeguards, Office of Nuclear Material Safety and Safeguards. [FR Doc. E5-2919 Filed 6-7-05; 8:45 am] BILLING CODE 7590-01-P POSTAL SERVICE Postal Service Board of Governors; Sunshine Act Meeting Date and Times: Tuesday, June 14, 2005; 9 a.m. and 3 p.m. Place: Washington, DC, at U.S. Postal Service Headquarters, 475 L'Enfant Plaza, SW., in the Benjamin Franklin Room. Status: June 14-9 a.m. (closed); 3 p.m. (open). Matters to be considered: Tuesday, June 14 at 9 a.m. (Closed) 1. Strategic Planning. 2. Personnel Matters and Compensation Issues. 3. Financial Update. 4.Capital Investments. a. Flat Recognition Improvement Program Phase 2. b. Postal Automated Redirection System Phase 2. c. Modification to Automated Package Processing System. 5. Rate Case Planning. 6. Postal Rate Commission Decision on Negotiated Service Agreement with HSBC North America Holdings, Inc./Household International, Docket No. MC2005-2. 7. Proposed Filing with the Postal Rate Commission for a Negotiated Service Agreement. Tuesday, June 14 at 3 p.m.

(Open)1. Minutes of the Previous Meeting, May 10-11, 2005. 2. Remarks of the Postmaster General and CEO Jack Potter. 3. Committee Reports. 4. Capital Investments. a. 1,406 Tractors and 382 Spotters. b. 3,120 Carrier Route Vehicles. 5. Tentative Agenda for the August 1-2, 2005, meeting in Newport Beach, California. Contact Person for More Information: William T. Johnstone, Secretary of the Board, U.S. Postal Service, 475 L'Enfant Plaza, SW., Washington, DC 20260-1000. Telephone

(202)268-4800. William T. Johnstone, Secretary. [FR Doc. 05-11471 Filed 6-6-05; 8:45 am]

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