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]
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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
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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.
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]
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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
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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.
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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
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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
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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.
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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.
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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]
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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
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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