Notices. DEPARTMENT OF LABOR

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A research copy — for the controlling text, always check the official state or federal source. Not legal advice.

BILLING CODE 7020-02-P DEPARTMENT OF LABOR Office of the Assistant Secretary for Veterans Employment and Training President's National Hire Veterans Committee; Notice of Open Meeting The President's National Hire Veterans Committee was established under 38 U.S.C. 4100 Public Law 107-288, Jobs for Veterans Act, to furnish information to employers with respect to the training and skills of veterans and disabled veterans, and to the advantages afforded employers by hiring veterans with training and skills and to facilitate the employment of veterans and disabled veterans through participation in Career One Stop National Labor Exchange, and other means.

The President's National Hire Veterans Committee will meet on Thursday, February 23, 2006 beginning at 1 p.m. at the Omni Hotel, 245 Water Street, Jacksonville, Florida. The committee will discuss raising corporate awareness as to the advantages of hiring veterans. Individuals needing special accommodations should notify Bill Offutt at

(202)693-4717 by February 16, 2006. Signed in Washington, DC, this 23rd day of January 2006. Charles S. Ciccolella, Assistant Secretary, Veterans Employment and Training. [FR Doc. E6-1610 Filed 2-6-06; 8:45 am] BILLING CODE 4510-79-P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50-247 and 50-286; License Nos. DPR-26 and DPR-64; EA-05-190] In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Unit Nos. 2 and 3); Confirmatory Order Modifying License (Effective Immediately) I Entergy Nuclear Operations, Inc. (Licensee) is the holder of Facility Operating License Nos. DPR-26 and DPR-64 issued by the Nuclear Regulatory Commission (NRC or Commission) pursuant to 10 CFR part 50. The licenses authorize the operation of Indian Point Nuclear Generating Unit Nos. 2 and 3, in accordance with the conditions specified therein. The facilities are located on the Licensee's site in Buchanan, New York. II The Energy Policy Act of 2005

(Act)(see 42 U.S.C. 2210 *et seq.* ) was enacted on August 8, 2005. Section 651(b) of the Act states: For any licensed nuclear power plants located where there is a permanent population, as determined by the 2000 decennial census, in excess of 15,000,000 within a 50-mile radius of the power plant, not later than 18 months after enactment of this Act, the Commission shall require that backup power to be available for the emergency notification system of the power plant, including the emergency siren warning system, if the alternating current supply within the 10-mile emergency planning zone of the power plant is lost. Public Law 109-58, 119 Stat 594. Indian Point Nuclear Generating Unit Nos. 2 and 3 meet the criteria of the Act. Adequate backup power for the emergency notification system (ENS), as required by section 651(b) of the Act, requires that:

(a)The backup power supply for the Public Alerting System

(PAS)must meet commonly-applicable standards, such as National Fire Protection Association

(NFPA)Standard 1221, Standard for the Installation, Maintenance, and Use of Emergency Communications Systems

(2002)and Underwriters Laboratory

(UL)2017, section 58.2;

(b)each PAS and PAS Alerting Appliance (PASAA) must receive adequate power to perform their intended functions such that backup power is sufficient to allow operation in standby mode for a minimum of 24 hours and in alert mode for a minimum of 15 minutes;

(c)batteries used for backup power must recharge to at least 80 percent of their capacity in no less than 24 hours;

(d)except for those components that are in facilities staffed on a continuous basis (24 hours per day, 7 days per week) or otherwise monitored on a continuous basis, immediate automatic indication of a loss of power must be provided to the Licensee and appropriate government agencies; and

(e)except for those components that are in facilities staffed on a continuous basis (24 hours per day, 7 days per week) or otherwise monitored on a continuous basis, an automatic notification of an unplanned loss of power must be made to the Licensee in sufficient time to take compensatory action before the backup power supply can not meet the requirements of section IV, part II. A. 2. III In order to carry out the statutory mandate discussed above, the Commission has determined that the operating licenses for Indian Point Nuclear Generating Unit Nos. 2 and 3 must be modified to include provisions with respect to the measures identified in section II of this Order. The requirements needed to effectuate the foregoing are set forth in section IV below. On January 31, 2006, the Licensee consented to the license modifications set forth in Section IV below. The Licensee further agreed in its letter dated January 31, 2006, that it has waived its right to a hearing on this Order, and, therefore, that the terms of the Order are effective upon issuance. I find that the license modifications set forth in section IV are acceptable and necessary, and conclude that with these provisions the Licensee will be in compliance with the intent of the Act. Based on the above and Licensee's consent, this Order is immediately effective upon issuance. IV Accordingly, pursuant to sections 104b, 161b, 161i, 161o, 182 and 186 of the Atomic Energy Act of 1954, as amended, section 651(b) of the Energy Policy Act of 2005 (Pub. L. 109-58, 119 Stat 594), and the Commission's regulations in 10 CFR 2.202 and 10 CFR part 50, *It is hereby ordered,* Effective Immediately, that License Nos. DPR-26 and DPR-64 Are Modified as Follows: I. The Licensee shall provide and maintain a backup power supply for the ENS for the Indian Point Nuclear Generating Unit Nos. 2 and 3, facilities. The ENS is the primary prompt notification system used to alert the public of an event at a nuclear power plant. II. The Licensee shall implement II.A, II.B, and II.C.1-3 by January 30, 2007. The backup power system for the ENS shall be declared operable by January 30, 2007. The backup power supply for the ENS shall include, as a minimum: A.1. A backup power supply for the PAS and each PASAA which shall provide adequate power for each component to perform their design function. These functions include the following as examples: sound output, rotation, speech intelligibility, or brightness as applicable. This criterion includes the associated activation, control, monitoring, and testing components for the backup power supply to the ENS including, but not limited to: radio transceivers, testing circuits, sensors to monitor critical operating parameters of the PAS and PASAA. The Licensee is required to meet all applicable standards, such as NFPA Standard 1221, Standard for the Installation, Maintenance, and Use of Emergency Communications Systems

(2002)and UL 2017, Section 58.2; 2. The backup power supply for each PAS and PASAA shall be designed for operation in standby mode, including, but not limited to: radio transceivers, testing circuits, sensors fully operational and providing polling data to the activation, control, monitoring, and test system for at least 24 hours without AC supply power from the local electric distribution grid. The backup power supply then shall be capable of performing its intended function, without recharge, by operating the PAS and PASAA in its alerting mode at its full design capability for a period of at least 15 minutes. This sequence shall be assumed to occur at the most unfavorable environmental conditions including, but not limited to, temperature, wind, and precipitation specified for PAS and PASAA operation and assume that the batteries are approaching the end of their design life ( *i.e.* , the ensuing recharge cycle will bring the batteries back to the minimum state that defines their design life). 3. In defining battery design life, automatic charging shall be sized such that batteries in the backup power are fully recharged to at least 80 percent of their maximum rated capacity from the fully discharged state in a period of not more than 24 hours. 4. Battery design life and replacement frequency shall comply with vendor(s) recommendations. 5. Except for those components that are in facilities staffed on a continuous basis (24 hours per day, 7 days per week) or otherwise monitored on a continuous basis, there shall be a feedback system(s) that provides immediate automatic indication of a loss of power to the Licensee and the appropriate government agencies, and an automatic notification of an unplanned loss of power must be made to the Licensee in sufficient time to take compensatory action before the backup power supply can not meet the requirements of section IV, part II. A. 2. 6. The Licensee shall implement a preventative maintenance and testing program of the ENS including, but not limited to: the equipment that activates and monitors the system, equipment that provides backup power, and the alerting device to ensure the ENS system performs to its design specifications. B.1. The Licensee shall implement any new Department of Homeland Security

(DHS)guidance pertaining to backup power for ENS that may affect the system requirements outlined in this Order that is issued prior to obtaining DHS approval of the alerting system design. The Licensee shall not implement any DHS guidance that reduces the effectiveness of the ENS as provided for in this Order without prior NRC approval. 2. The Licensee shall document the evaluation of lessons learned from any evaluation of the current alert and notification system

(ANS)and address resolution of identified concerns when designing the backup power system and such consideration shall be included in the design report. 3. The final PAS design must be submitted to DHS for approval prior to May 1, 2006. C.1. Within 60 days of the issuance of this Order, the Licensee shall submit a response to this Order to the NRC Document Control Desk providing a schedule of planned activities associated with the implementation of the Order including interactions with the Putnam, Rockland, Westchester, and Orange Counties, the State of New York, and DHS. In addition, the Licensee shall provide a progress report on or shortly before June 30, 2006. 2. The Licensee shall submit a proposed revision to its emergency response plan to incorporate the implementation of items A.1-A.6, B.1-B.3, and C.4-C.5. This plan shall be submitted to the NRC for review and approval within 120 days from the issuance of the Order. 3. Prior to declaring the ENS operable, the Licensee shall, in accordance with a test plan submitted to and approved by the NRC in conjunction with the design submittal, demonstrate satisfactory performance of all (100%) of the ENS components including the ability of the backup power supply to meet its design requirements. 4. After declaring the ENS operable, the Licensee shall conduct periodic testing to demonstrate reliable ENS system performance. 5. The results from testing as discussed in paragraph C.4 shall be reported, in writing, to the NRC Document Control Desk, with a copy to the Director of Nuclear Reactor Regulation, documenting the results of each test, until there are 3 consecutive tests testing the operability of all ENS components used during an actual activation), conducted no sooner than 25 days and no more than 45 days from the previous test with a 97% overall entire emergency planning zone success rate with no individual county failure rate greater than 10%. A false negative report from a feedback system will constitute a siren failure for the purposes of this test. III. The Licensee shall submit a written report to the NRC Document Control Desk, with a copy to the Director of Nuclear Reactor Regulation, when the ENS is declared operable. IV. The Licensee shall submit a written report to the NRC Document Control Desk and provide a copy to the Director of Nuclear Reactor Regulation when it has achieved full compliance with the requirements contained in this Order. V. The Licensee may use the criteria contained in 10 CFR 50.54(q) to make changes to the requirements contained in this Order without prior NRC approval provided that they do not reduce the effectiveness of the Order requirements or the approved emergency plan. The Licensee shall notify, in writing, the NRC Document Control Desk, with a copy to the Director, Division of Preparedness and Response, Office of Nuclear Security and Incident Response, 30 days in advance of implementing such a change. For other changes, the Licensee may submit a request, in writing, to the NRC Document Control Desk, with a copy to the Director, Office of Nuclear Reactor Regulation, to relax or rescind any of the above requirements upon a showing of good cause by the Licensee. V Any person adversely affected by this Confirmatory Order, other than the Licensee, may request a hearing within 20 days of its issuance. Where good cause is shown, consideration will be given to extending the time to request a hearing. A request for extension of time must be made in writing to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and include a statement of good cause for the extension. Any request for a hearing shall be submitted to the Secretary, U.S. Nuclear Regulatory Commission, ATTN: Chief, Rulemakings and Adjudications Staff, Washington, DC 20555. Copies of the hearing request shall also be sent to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555; to the Assistant General Counsel for Materials Litigation and Enforcement at the same address; to the Regional Administrator, NRC Region I, U.S. NRC Region I, 475 Allendale Road, King of Prussia, PA 19406-1415; and to the Licensee, Entergy Nuclear Operations, Inc., 440 Hamilton Avenue, White Plains, NY 10601. Because of continuing disruptions in delivery of mail to United States Government offices, it is requested that answers and requests for hearing or for time extensions be transmitted to the Secretary of the Commission either by means of facsimile transmission to 301-415-1101, or by e-mail to *hearingdocket@nrc.gov,* and also to the Office of the General Counsel either by means of facsimile transmission to 301-415-3725 or by e-mail to *OGCMailCenter@nrc.gov.* If a person other than the Licensee requests a hearing, that person shall set forth with particularity the manner in which his interest is adversely affected by this Order and shall address the criteria set forth in 10 CFR 2.309. If the hearing is requested by a person whose interest is adversely affected, the Commission will issue an Order designating the time and place of any hearing. If a hearing is held, the issue to be considered at such hearing shall be whether this Confirmatory Order should be sustained. In the absence of any request for hearing or written approval of an extension of time in which to request a hearing, the provisions specified in section IV above shall be final 20 days from the date of this Order without further order or proceedings. If an extension of time for requesting a hearing has been approved, the provisions specified in section IV shall be final when the extension expires if a hearing request has not been received. *An Answer or a Request for Hearing Shall Not Stay the Immediate Effectiveness of this Order.* For The Nuclear Regulatory Commission. Dated this 31st day of January 2006. J.E. Dyer, Director, Office of Nuclear Reactor Regulation. [FR Doc. E6-1626 Filed 2-6-06; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION [Docket No. 50-139; EA-05-230] In the Matter of the University of Washington; (The University of Washington Research Reactor); Order Modifying Requirements for Dismantling of Facility and Disposition of Component Parts I The University of Washington (UW or the licensee) is the holder of Facility License No. R-73 issued by the Nuclear Regulatory Commission (NRC or Commission) pursuant to 10 CFR part 50. The license authorizes possession but not operation of the UW Research Reactor (the facility) in accordance with conditions specified therein. The facility is located on the licensee's campus in Seattle, Washington. II By application dated August 2, 1994, the licensee requested authorization to dismantle the UW Research Reactor and to dispose of the component parts, in accordance with the decommissioning plan

(DP)submitted as part of the application. The NRC reviewed the application with respect to the provisions of the Commission's rules and regulations and found that the dismantling and disposal of component parts as stated in the licensee's DP are consistent with the regulations in 10 CFR Chapter 1 and are not inimical to the common defense and security or to the health and safety of the public. On May 1, 1995, the Commission issued an “Order Authorizing Dismantling of Facility and Disposition of Component Parts” (the 1995 order) to the licensee to dismantle the UW Research Reactor facility covered by Facility License No. R-73, as amended, and dispose of the component parts in accordance with its DP and the Commission's rules and regulations. By letter dated October 27, 2004, as supplemented on March 18 and September 28, 2005, the licensee requested that the NRC amend the 1995 order to allow the licensee to make certain changes to the DP without prior NRC approval. III The licensee requested that the provisions of 10 CFR 50.59 be made applicable to the DP for the UW Research Reactor to allow the licensee to make certain changes to the DP without prior Commission approval. The licensee made this request to allow flexibility during decommissioning in making changes which are of minimal significance to safety. At the time the UW DP was approved, the DP was a stand-alone document approved by the order. The DP was not part of the safety analysis report and there was no process in the DP or the 1995 order to allow changes to be made to the DP without prior Commission approval. The UW was ordered to dismantle the facility and dispose of the component parts in accordance with the DP and the Commission's rules and regulations. The regulations in 10 CFR 50.59 did not apply to the UW DP because 10 CFR 50.59 applies to changes to the facility safety analysis report. In addition, 10 CFR 50.59 does not apply to the UW reactor, because it no longer is authorized to operate. In a request for additional information, the staff asked the licensee to propose wording for making changes to the UW DP. The staff also asked the licensee to identify the sections of the DP that would not be subject to the proposed change process and would require prior Commission approval to be made. The NRC staff has reviewed the proposed change process by the licensee and concludes that it will allow the licensee to make changes to the DP without prior Commission approval consistent with the intent of the 10 CFR 50.59 process. Therefore, the licensee's proposed change process is acceptable to the staff. The staff has also reviewed the sections of the DP that the licensee proposes not to change without prior Commission approval. These sections concern the DECON decommissioning option chosen by the licensee, the criteria proposed by the licensee and approved by the Commission for unrestricted release of the facility and the site, the Technical and Safety Committee, which is a requirement of the technical specifications, and the radiation exposure limits, which are a requirement of the regulations in 10 CFR part 20. Therefore the licensee's proposed list of DP sections not subject to the change process is acceptable to the staff. IV Accordingly, pursuant to sections 104c, 161b, 161i, 161o, 182, and 186 of the Atomic Energy Act of 1954, as amended, and the Commission's regulations in 10 CFR 2.202 and 10 CFR part 50, *It is hereby ordered that* : The University of Washington Nuclear Reactor Decommissioning Plan dated July 1994 be modified to add the following: 10.0 Decommissioning Plan Change Process

(a)Definitions for the purposes of this section:

(1)Change means a modification or addition to, or removal from, the facility or procedures that affects a design function, method of performing or controlling the function, or an evaluation that demonstrates that intended functions will be accomplished.

(2)Departure from a method of evaluation described in the Decommissioning Plan (as updated) used in establishing the design bases or in the safety analyses means:

(i)Changing any of the elements of the method described in the Decommissioning Plan (as updated) unless the results of the analysis are conservative or essentially the same; or

(ii)Changing from a method described in the Decommissioning Plan to another method unless that method has been approved by NRC for the intended application.

(3)Facility as described in the Decommissioning Plan (as updated) means:

(i)The structures, systems, and components

(SSC)that are described in the Decommissioning Plan (as updated),

(ii)The design and performance requirements for such SSCs described in the Decommissioning Plan (as updated), and

(iii)The evaluations or methods of evaluation included in the Decommissioning Plan (as updated) for such SSCs which demonstrate that their intended function(s) will be accomplished.

(4)Decommissioning Plan (as updated) means the Decommissioning Plan submitted and approved by the Commission, as amended and supplemented, and as updated per the requirements of Sec. 50.71, as applicable.

(5)Procedures as described in the Decommissioning Plan (as updated) means those procedures that contain information described in the Decommissioning Plan (as updated) such as how structures, systems, and components are operated and controlled (including assumed operator actions and response times).

(6)Tests or experiments not described in the Decommissioning Plan (as updated) means any activity where any structure, system, or component is utilized or controlled in a manner which is either:

(i)Outside the reference bounds of the design bases as described in the Decommissioning Plan (as updated) or

(ii)Inconsistent with the analyses or descriptions in the Decommissioning Plan (as updated). (b)(1) The University may make changes in the facility as described in the Decommissioning Plan (as updated), make changes in the procedures as described in the Decommissioning Plan (as updated), and conduct tests or experiments not described in the Decommissioning Plan (as updated) without obtaining Commission approval only if:

(i)A change to the technical specifications incorporated in the license is not required, and

(ii)The change, test, or experiment does not meet any of the criteria in paragraph (b)(2) of this section.

(2)The University shall obtain Commission approval prior to implementing a proposed change, test, or experiment if the change, test, or experiment would:

(i)Result in more than a minimal increase in the frequency of occurrence of an accident previously evaluated in the Decommissioning Plan (as updated);

(ii)Result in more than a minimal increase in the likelihood of occurrence of a malfunction of a structure, system, or component

(SSC)important to safety previously evaluated in the Decommissioning Plan (as updated);

(iii)Result in more than a minimal increase in the consequences of an accident previously evaluated in the Decommissioning Plan (as updated);

(iv)Result in more than a minimal increase in the consequences of a malfunction of an SSC important to safety previously evaluated in the Decommissioning Plan (as updated);

(v)Create a possibility for an accident of a different type than any previously evaluated in the Decommissioning Plan (as updated);

(vi)Result in a departure from a method of evaluation described in the Decommissioning Plan (as updated) used in establishing the design bases or in the safety analyses.

(3)In implementing this paragraph, the Decommissioning Plan (as updated) is considered to include Decommissioning Plan changes pursuant to this condition and changes ordered by the Commission.

(4)The provisions in this section do not apply to changes to the facility or procedures when the applicable regulations establish more specific criteria for accomplishing such changes. (c)(1) The licensee shall maintain records of changes in the facility, of changes in procedures, and of tests and experiments made pursuant to paragraph

(b)of this section. These records must include a written evaluation which provides the bases for the determination that the change, test, or experiment does not require Commission approval pursuant to paragraph (b)(2) of this section.

(2)The licensee shall submit, as specified in 10 CFR 50.4, a report containing a brief description of any changes, tests, and experiments, including a summary of the evaluation of each. A report must be submitted at intervals not to exceed 24 months.

(3)The records of changes in the facility must be maintained until the termination of a license issued pursuant to 10 CFR Part 50. Records of changes in procedures and records of tests and experiments must be maintained for a period of 5 years.

(d)The following sections of the Decommissioning Plan (as amended) are not subject to the Decommissioning Plan change process: 1.3.1, 2.1, 1.3.7.1, 1.3.7.2, 2.6, 2.3.2, and 3.2.2. V Any person adversely affected by this Order may request a hearing on this Order within 20 days of the date of this Order. Where good cause is shown, consideration will be given to extending the time to request a hearing. A request for an extension must be made in writing to the Director, Office of Nuclear Reactor Regulation, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and must include a statement of good cause for the extension. A request for a hearing or a petition for leave to intervene must be filed

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

(3)by e-mail addressed to the Office of the Secretary, U.S. Nuclear Regulatory Commission, *hearingdocket@nrc.gov* ; or

(4)by 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 (the 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 NRC requests that copies be transmitted either by 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 licensee. The licensee's contact for this is Stanley J. Addison, UW Radiation Safety Officer, University of Washington, Environmental Health and Safety, 201 Hall Health Center, Box 354400, Seattle, Washington 98195-4400. If a person other than the licensee requests a hearing, he or she shall set forth with particularity the manner in which his or her interest is adversely affected by this Order and shall address the criteria set forth in 10 CFR 2.309. If a hearing is requested by the licensee or a person whose interest is adversely affected, the Commission will issue an order designating the time and place of any hearing. If a hearing is held, the issue to be considered at such hearing shall be whether this Order should be sustained. In the absence of any request for a hearing or written approval of an extension of time in which to request a hearing, the provisions specified in section IV above shall be effective and final 20 days from the date of this Order without further order or proceedings. If an extension of time for requesting a hearing has been approved, the provisions specified in section IV shall be final when the extension expires if a hearing request has not been received. For further information see the application from the licensee dated October 27, 2004 (ML043090558), as supplemented on March 18 (ML050900307) and September 28, 2005 (ML052770539), and the staff's safety evaluation dated January 31, 2006 (ML052910487), 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 (ADAMS) Public Electronic Reading Room on the Internet at the NRC Web site, *http://www.nrc.gov/reading-rm/adams.html* (use the ADAMS ML numbers given above). Persons who do not have access to ADAMS or who have problems in accessing the documents 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* . For the Nuclear Regulatory Commission. Dated this 31st day of January 2006. Christopher I. Grimes, Director, Division of Policy and Rulemaking, Office of Nuclear Reactor Regulation. [FR Doc. E6-1625 Filed 2-6-06; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION Advisory Committee on Reactor Safeguards; Subcommittee Meeting on Thermal-Hydraulic Phenomena; Notice of Meeting The ACRS Subcommittee on Thermal-Hydraulic Phenomena will hold a meeting on February 14-16, 2006, Room T-2B3, 11545 Rockville Pike, Rockville, Maryland. The entire meeting will be open to public attendance, with the exception of portions that may be closed to discuss that is proprietary to various equipment vendors pursuant to 5 U.S.C. 552b(c)(4). The agenda for the subject meeting shall be as follows: *Tuesday, February 14, 2006—8:30 a.m. until the conclusion of business.* *Wednesday, February 15, 2006—8:30 a.m. until the conclusion of business.* *Thursday, February 16, 2006—8:30 a.m. until the conclusion of business.* The Subcommittee will discuss and hear a briefing from the NRC staff, the Nuclear Energy Institute (NEI), and other interested stakeholders regarding recent work related to chemical effects in containment sumps during loss of coolant accident events, and licensee responses to Generic Letter 2004-02 concerning pressurized water reactor sumps. The Subcommittee will hear presentations by and hold discussions with representatives of the NRC staff, NEI, licensees, contractors, and other interested persons regarding this matter. The Subcommittee will gather information, analyze relevant issues and facts, and formulate proposed positions and actions, as appropriate, for deliberation by the full Committee. Members of the public desiring to provide oral statements and/or written comments should notify the Designated Federal Official, Mr. Ralph Caruso (Telephone: 301-415-8065) five days prior to the meeting, if possible, so that appropriate arrangements can be made. Electronic recordings will be permitted only during those portions of the meeting that are open to the public. Further information regarding this meeting can be obtained by contacting the Designated Federal Official between 7:30 a.m. and 4:15 p.m. (ET). Persons planning to attend this meeting are urged to contact the above named individual at least two working days prior to the meeting to be advised of any potential changes to the agenda. Dated: February 1, 2006. Michael L. Scott, Branch Chief, ACRS/ACNW. [FR Doc. E6-1628 Filed 2-6-06; 8:45 am] BILLING CODE 7590-01-P NUCLEAR REGULATORY COMMISSION Sunshine Act Meeting Agency Holding the Meetings: Nuclear Regulatory Commission. Date: Weeks of February 6, 13, 20, 27, March 6, 13, 2006. Place: Commissioners' Conference Room, 11555 Rockville Pike, Rockville, Maryland. Status: Public and closed. Matters To Be Considered: Week of February 6, 2006 Monday, February 6, 2006 9:30 a.m. Briefing on Materials Degradation Issues and Fuel Reliability (Public Meeting), (Contact: Jennifer Uhle, 301-415-6200). This meeting will be webcast live at the Web address *http://www.nrc.gov* . 2 p.m. Discussion of Security Issues (Closed—Ex. 1). Wednesday, February 8, 2006 9:30 a.m. Briefing on Office of Nuclear Materials Safety and Safeguards

(NMSS)Programs, Performance, and Plans—Materials Safety (Public Meeting) (Contact: Teresa Mixon, 301-415-7474; Derek Widmayer, 301-415-6677). This meeting will be webcast live at the Web address *http://www.nrc.gov* . 1:30 p.m. Briefing on Office of Research

(RES)Programs, Performance and Plans (Public Meeting) (Contact: Gene Carpenter, 301-415-7333). This meeting will be webcast live at the Web address *http://www.nrc.gov* . Week of February 13, 2006—Tentative Tuesday, February 14, 2006 2 p.m. Briefing on Office of Nuclear Materials Safety and Safeguards

(NMSS)Programs, Performance, and Plans—Waste Safety (Public Meeting) (Contact: Teresa Mixon, 301-415-7474; Derek Widmayer, 301-415-6677). This meeting will be webcast live at the Web address *http://www.nrc.gov* . Wednesday, February 15, 2006 9:30 a.m. Briefing on Office of Chief Financial Officer

(CFO)Programs, Performance, and Plans (Public Meeting), (Contact: Edward New, 301-415-5646) This meeting will be webcast live at the Web address *http://www.nrc.gov* . Week of February 20, 2006—Tentative There are no meetings scheduled for the Week of February 20, 2006. Week of February 27, 2006—Tentative There are no meetings scheduled for the Week of February 27, 2006. Week of March 6, 2006—Tentative There are no meetings scheduled for the Week of March 6, 2006. Week of March 13, 2006—Tentative Monday, March 13, 2006 1:30 p.m. Briefing on Office of Information Services

(OIS)Programs, Performance, and Plans (Public Meeting), (Contact: Edward Baker, 301-415-8700). This meeting will be webcast live at the Web address *http://www.nrc.gov* . Wednesday, March 15, 2006 9:30 a.m. Briefing on Office of Nuclear Security and Incident Response

(NSIR)Programs, Performance, and Plans (Public Meeting), (Contact: Evelyn S. Williams, 301-415-7011) This meeting will be webcast live at the Web address *http://www.nrc.gov* . 1:30 p.m. Discussion of Security Issues (Closed—Ex. 1 & 3). Thursday, March 16, 2006 9:30 a.m. Briefing on Office of Nuclear Reactor Regulation (NRR— Programs, Performance, and Plans (Public Meeting), (Contact: Cynthia Carpenter, 301-415-1275). This meeting will be webcast live at the Web address *http://www.nrc.gov* . *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: February 2, 2006. R. Michelle Shroll, Office of the Secretary. [FR Doc. 06-1161 Filed 2-3-06; 13:54 pm]

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