In the Matter of Entergy Nuclear Operations, Inc. (Indian Point Nuclear Generating Unit Nos. 2 and 3); Confirmatory Order Modifying License (Effective Immediately), 6290-6292 [E6-1626]

Download as PDF 6290 Federal Register / Vol. 71, No. 25 / Tuesday, February 7, 2006 / Notices INTERNATIONAL TRADE COMMISSION [Investigation Nos. 731–TA–457–A–D (Second Review)] Heavy Forged Hand Tools From China Determinations On the basis of the record 1 developed in the subject five-year reviews, the United States International Trade Commission (Commission) determines, pursuant to section 751(c) of the Tariff Act of 1930 (19 U.S.C. 1675(c)) (the Act), that revocation of the antidumping duty orders on heavy forged hand tools from China would be likely to lead to continuation or recurrence of material injury to industries in the United States within a reasonably foreseeable time. The Commission instituted these reviews on July 1, 2005 (70 FR 38197) and determined on October 4, 2005 that it would conduct expedited reviews (70 FR 61156, October 20, 2005). The Commission transmitted its determinations in these reviews to the Secretary of Commerce on January 31, 2006. The views of the Commission are contained in USITC Publication 3836 (January 2006), entitled Heavy Forged Hand Tools from China: Investigation Nos. 731–TA–457 (Second Review). By order of the Commission. Issued: February 1, 2006. Marilyn R. Abbott, Secretary to the Commission. [FR Doc. E6–1637 Filed 2–6–06; 8:45 am] BILLING CODE 7020–02–P INTERNATIONAL TRADE COMMISSION [USITC SE–06–011] Sunshine Act Meeting Notice erjones on PROD1PC68 with NOTICES By order of the Commission: Issued: February 3, 2006. Marilyn R. Abbott, Secretary to the Commission. [FR Doc. 06–1176 Filed 2–3–06; 2:00 pm] BILLING CODE 7020–02–P Background AGENCY HOLDING THE MEETING: International Trade Commission. TIME AND DATE: February 23, 2006 at 11 a.m. PLACE: Room 101, 500 E Street SW., Washington, DC 20436. Telephone: (202) 205–2000. STATUS: Open to the public. MATTERS TO BE CONSIDERED: 1. Agenda for future meetings: none. 2. Minutes. 3. Ratification List. 4. Inv. Nos. 701–TA–401 and 731– TA–853 and 854 (Second Review) 1 The record is defined in sec. 207.2(f) of the Commission’s Rules of Practice and Procedure (19 CFR 207.2(f)). VerDate Aug<31>2005 (Structural Steel Beams from Japan and Korea)—briefing and vote. (The Commission is currently scheduled to transmit its determination and Commissioners’ opinions to the Secretary of Commerce on or before March 8, 2006.). 5. Outstanding action jackets: none. In accordance with Commission policy, subject matter listed above, not disposed of at the scheduled meeting, may be carried over to the agenda of the following meeting. 15:23 Feb 06, 2006 Jkt 208001 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. DEPARTMENT OF LABOR II Office of the Assistant Secretary for Veterans Employment and Training 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: 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 PO 00000 Frm 00042 Fmt 4703 Sfmt 4703 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 E:\FR\FM\07FEN1.SGM 07FEN1 Federal Register / Vol. 71, No. 25 / Tuesday, February 7, 2006 / Notices 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. erjones on PROD1PC68 with NOTICES 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 VerDate Aug<31>2005 15:23 Feb 06, 2006 Jkt 208001 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 PO 00000 Frm 00043 Fmt 4703 Sfmt 4703 6291 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. E:\FR\FM\07FEN1.SGM 07FEN1 6292 Federal Register / Vol. 71, No. 25 / Tuesday, February 7, 2006 / Notices 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. erjones on PROD1PC68 with NOTICES 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 VerDate Aug<31>2005 15:23 Feb 06, 2006 Jkt 208001 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 PO 00000 Frm 00044 Fmt 4703 Sfmt 4703 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 E:\FR\FM\07FEN1.SGM 07FEN1

Agencies

[Federal Register Volume 71, Number 25 (Tuesday, February 7, 2006)]
[Notices]
[Pages 6290-6292]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E6-1626]


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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

[[Page 6291]]

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.

[[Page 6292]]

    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
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