In the Matter of Entergy Nuclear Operations, Inc; Indian Point Nuclear Generating Unit Nos. 2 and 3; Order Modifying License (Effective Immediately), 43666-43669 [E7-15191]
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sroberts on PROD1PC70 with NOTICES
43666
Federal Register / Vol. 72, No. 150 / Monday, August 6, 2007 / Notices
2. The title of the information
collection: NRC Form 4, ‘‘Cumulative
Occupational Dose History’’ and NRC
Form 5, ‘‘Occupational Exposure Record
for a Monitoring Period’’.
3. The form number if applicable:
NRC Form 4 (3150–0005) and NRC
Form 5 (3150–0006).
4. How often the collection is
required: NRC Form 4: Occasionally;
NRC Form 5: Annually.
5. Who is required or asked to report:
NRC licensees who are required to
comply with 10 CFR part 20.
6. An estimate of the number of
annual responses: NRC Form 4: 20,024
(19,822 from reactor sites and 202 from
material licensees) and NRC Form 5:
172,419 (160,701 from reactor sites and
11,718 from material licensees.
7. The estimated number of annual
respondents: NRC Form 4: 218 (104
from reactor sites and 114 from
materials licensees) and NRC Form 5:
4,212 (104 reactor sites and 114
materials licensees, plus an additional
3,994 materials licensees
recordkeepers).
8. An estimate of the total number of
hours needed annually to complete the
requirement or request: NRC Form 4:
10,012 hours on an average of 0.5 hours
per response; NRC Form 5: 65,618 hours
(56,898 hours for recordkeeping on an
average of 0.33 hours per record and
8,720 hours for reporting on an average
of 40 hours per licensee).
9. An indication of whether Section
3507(d), Public Law 104–13 applies: N/
A.
10. Abstract: NRC Form 4 is used to
record the summary of an individual’s
cumulative occupational radiation dose
up to and including the current year to
ensure that the dose does not exceed
regulatory limits.
NRC Form 5 is used to record and
report the results of individual
monitoring for occupational radiation
exposure during a one-year (calendar
year) period to ensure regulatory
compliance with annual radiation dose
limits.
A copy of the final supporting
statement may be viewed free of charge
at the NRC Public Document Room, One
White Flint North, 11555 Rockville
Pike, Room O–1 F21, Rockville, MD
20852. OMB clearance requests are
available at the NRC worldwide Web
site: https://www.nrc.gov/public-involve/
doc-comment/omb/. The
document will be available on the NRC
home page site for 60 days after the
signature date of this notice.
Comments and questions should be
directed to the OMB reviewer listed
below by September 5, 2007. Comments
received after this date will be
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considered if it is practical to do so, but
assurance of consideration cannot be
given to comments received after this
date.
Nathan Frey, Desk Officer, Office of
Information and Regulatory Affairs
(3150–0005 and 3150–0006), NEOB–
10202, Office of Management and
Budget, Washington, DC 20503.
Comments can also be e-mailed to
Nathan.Frey@omb.eop.gov or submitted
by telephone at (202) 395–4650.
The NRC Clearance Officer is
Margaret A. Janney, 301–415–7245.
Dated at Rockville, Maryland, this 30th day
of July, 2007.
For the Nuclear Regulatory Commission.
Christopher Colburn,
Acting NRC Clearance Officer, Office of
Information Services.
[FR Doc. E7–15190 Filed 8–3–07; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–247 and 50–286; License
Nos. DPR–26 and DPR–64; EA–07–189]
In the Matter of Entergy Nuclear
Operations, Inc; Indian Point Nuclear
Generating Unit Nos. 2 and 3; 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
On April 23, 2007, the NRC issued to
Entergy Nuclear Operations, Inc.
(Entergy) a Notice of Violation (NOV)
and Proposed Imposition of Civil
Penalty for a violation involving the
failure to meet the requirements of a
Confirmatory Order (EA–05–190) that
was issued to Entergy on January 31,
2006. On January 23, 2007, the NRC
granted Entergy’s request, provided in a
letter dated January 11, 2007, to extend
the full implementation date until April
15, 2007. The NRC issued the NOV and
Proposed Civil Penalty after Entergy
informed the NRC that the ‘‘radio only
activation’’ feature of the emergency
notification system (ENS) did not meet
its test acceptance criteria, resulting in
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the ENS not being fully operable by
April 15, 2007, the date it was required
to be operable. Entergy responded to the
NOV on May 23, 2007, and committed
to declaring the new ENS operable by
August 24, 2007. In its response,
Entergy admitted to the violation of the
Confirmatory Order, identified the
apparent causes of the violation, and
described corrective actions that were
taken or planned to correct the
violation.
Subsequent to the Licensee’s May 23,
2007, letter, the NRC held a public
meeting with Entergy officials on July 9,
2007, to clarify Entergy’s actions to
comply with the Confirmatory Order,
particularly with respect to ensuring
that the new ENS met the applicable
Federal Emergency Management Agency
(FEMA) regulations, as well as to ensure
that any specific county needs were
identified and addressed prior to
Entergy declaring the new ENS
operable.
The NRC has evaluated Entergy’s
response to the NOV and the additional
information gathered during the July 9,
2007, public meeting. The NRC has
determined that additional actions are
needed to ensure that the new ENS with
backup power supply capability is
operable by August 24, 2007, as
committed to in Entergy’s May 23, 2007
letter. These actions include:
Completing the outstanding
requirements delineated in the
aforementioned Confirmatory Order
issued January 31, 2006, as modified
herein; implementing those measures
necessary for FEMA to accept the new
ENS as the primary ENS for alerting the
public by August 24, 2007; and,
completing the necessary software and
procedure upgrades and training of
county personnel responsible for
actuation of the system.
III
Adequate backup power for the ENS,
as required by the Energy Policy Act of
2005 (Act) (see 42 U.S.C. 2210 et seq.)
Section 651(b), 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)
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batteries used for backup power must
recharge to at least 80 percent of their
capacity in a period of not more 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 of the
Confirmatory Order.
The requirements needed to
implement the foregoing are set forth in
Section IV below. Based on the above,
and in consideration of other
communications involving the NRC,
FEMA, New York State, the four
counties within the 10 mile Emergency
Planning Zone, and Entergy officials,
additional actions are needed to ensure
Entergy is in compliance with the
Commission’s requirements and that the
public interest will be protected.
Therefore, License Nos. DPR–26 and
DPR–64 should be modified to require
compliance with Section 651(b) of the
Act. Furthermore, pursuant to 10 CFR
2.202, and in consideration of the
ongoing violation of the Confirmatory
Order, as well as the prior enforcement
related to such, I find that the
significance of compliance with the Act
described above is such that the public
interest requires that this Order be
immediately effective.
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 meet all the
provisions contained in the January 31,
2006, Confirmatory Order (see
Appendix A of this Order), except as
specifically modified or supplemented
herein. With respect to the requirement
to provide and maintain an ENS with
backup power supply capability for the
Indian Point Nuclear Generating Unit
Nos. 2 and 3 facilities, the new ENS
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intended to comply with that
requirement shall meet applicable
requirements of state and federal
authorities such that it is declared
operable and placed into service as the
primary system by August 24, 2007.
II. The Licensee shall provide to NRC
within 7 days of this order a report
describing the steps and the expected
schedule for completing each of the
steps that the licensee understands are
necessary to meet applicable
requirements of state and federal
authorities to place the new ENS system
into service as the Primary Notification
system. The report should identify any
uncertainties in identification of
requirements or in schedules associated
with requirements.
III. Prior to declaring the new ENS
operable and using it as the primary
system, the Licensee shall: (a) Obtain
FEMA approval that the system, as
installed, meets the design criterion of
the approved ENS Design Report and is
in compliance with all applicable FEMA
regulations and guidance; and, (b)
complete all necessary software and
procedure upgrades and training of all
the four county response organizations,
accounting for the specific training
needs identified by the counties, in the
proper use of the new ENS and response
to associated alarming conditions.
IV. The Licensee shall maintain the
existing ENS fully available (including
conducting routine maintenance and
testing activities) and establish the
necessary procedures and actions to
enable its use as a backup to the new
ENS when the new ENS is declared in
use as the primary system, until such
time that FEMA grants approval to
remove the existing ENS from service.
The Director, Office of Enforcement,
may, in writing, relax or rescind any of
the above conditions upon
demonstration by the Licensee of good
cause.
V
In accordance with 10 CFR 2.202, the
Licensee must, and any other person
adversely affected by this Order may,
submit an answer to this Order within
20 days of its issuance. In addition, the
Licensee and any other person adversely
affected by this Order may request a
hearing on this Order 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 Enforcement, U.S. Nuclear Regulatory
Commission, Washington, DC 20555,
and include a statement of good cause
for the extension. Any answer or request
for a hearing shall be submitted to the
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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 Enforcement, to the Director, Office of
Nuclear Reactor Regulation, and to the
Assistant General Counsel for Materials
Litigation and Enforcement, U.S.
Nuclear Regulatory Commission,
Washington, DC 20555; 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, if the answer or
hearing request is by a person other than
the Licensee. 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(d).
If the 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.
Pursuant to 10 CFR 2.202(c)(2)(i), the
Licensee, may, in addition to
demanding a hearing, at the time the
answer is filed or sooner, move the
presiding officer to set aside the
immediate effectiveness of the Order on
the ground that the Order, including the
need for immediate effectiveness, is not
based on adequate evidence but on mere
suspicion, unfounded allegations, or
error.
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.
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Federal Register / Vol. 72, No. 150 / Monday, August 6, 2007 / Notices
Dated this 30th day of July 2007.
For the Nuclear Regulatory Commission.
Cynthia A. Carpenter,
Director, Office of Enforcement.
Appendix A—Section IV Excerpt From
NRC Confirmatory Order, Dated
January 31, 2006
sroberts on PROD1PC70 with NOTICES
IV
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
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(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,
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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
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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.
[FR Doc. E7–15191 Filed 8–3–07; 8:45 am]
BILLING CODE 7590–01–P
NUCLEAR REGULATORY
COMMISSION
[Docket Nos. 50–266, 50–301 Renewed
License Nos. DPR–24 and DPR–27]
In the Matter of Wisconsin Electric
Power Company and Nuclear
Management Company, LLC, (Point
Beach Nuclear Plant); Order Approving
Transfer of Licenses and Conforming
Amendments
I.
sroberts on PROD1PC70 with NOTICES
Wisconsin Electric Power Company
(WEPCO) and Nuclear Management
Company, LLC (NMC) are holders of the
Renewed Facility Operating Licenses
(FOLs), Nos. DPR–24 and DPR–27,
which authorize the possession, use and
operation of Point Beach Nuclear Plant,
Units 1 and 2 (Point Beach or facility).
NMC is licensed by the U.S. Nuclear
Regulatory Commission (NRC, the
Commission) to operate Point Beach.
WEPCO is licensed to possess Point
Beach with respect to WEPCO’s
ownership of the facility. Point Beach is
located near Two Rivers, Wisconsin.
II.
By letter dated January 26, 2007, as
supplemented by letter dated July 11,
2007, NMC, WEPCO and FPL Energy
Point Beach, LLC, (FPLE Point Beach)
submitted an application requesting
approval of the direct license transfers
that would be necessary in connection
with WEPCO’s proposed sale and
transfer to FPLE Point Beach of its 100
percent ownership interest in Point
Beach. The application also requested
the approval of the transfer of NMC’s
operating authority to FPLE Point
Beach. Transfer of the licenses will
authorize FPLE Point Beach, pursuant to
the general license in Section 72.210 of
Title 10 of the Code of Federal
Regulations (10 CFR), to store spent fuel
in the Independent Spent Fuel Storage
Installation (ISFSI) at Point Beach.
As a potential interim step towards
the sale of Point Beach, WEPCO and
FPLE Point Beach have signed an
Interim Operating Agreement that
would permit WEPCO, at its option, and
upon receipt of applicable regulatory
approvals, to transfer NMC’s operating
authority to FPLE Point Beach prior to
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the closing of the ownership sale of
Point Beach. This interim transfer of the
operating authority from NMC to FPLE
Point Beach would not change the
financial responsibilities or
qualifications or the decommissioning
funding status of WEPCO as the 100
percent owner of Point Beach.
WEPCO, NMC and FPLE Point Beach
requested approval of (1) conforming
license amendments that would reflect
the proposed transfer of ownership of
and operating authority for Point Beach
to FPLE Point Beach; and (2) the option
of transferring operating authority as an
interim step to FPLE Point Beach. The
amendments for transferring ownership
and operating authority would include
the following: (1) The deletion of the
references to WEPCO and NMC as
owner and operator of Point Beach,
respectively, and (2) the authorization of
FPLE Point Beach to possess, use, and
operate Point Beach under essentially
the same conditions and authorization
included in the existing licenses. Two
footnotes containing historical
references to the former licensees also
will be deleted. The applicants did not
propose any physical or operational
changes to the facility. After completion
of the proposed transfers, FPLE Point
Beach would be the owner and the
operator of Point Beach. The
amendments for transferring operational
authority as an interim step would
include the following: (1) The deletion
of the references to NMC as operator of
Point Beach, and replacement with
references to FPLE Point Beach, and (2)
the authorization of FPLE Point Beach
to operate Point Beach under essentially
the same conditions and authorization
included in the existing licenses. After
completion of the proposed transfers,
FPLE Point Beach would be the operator
of Point Beach.
The applicants requested approval of
the transfer of the renewed FOLs and
conforming license amendments
pursuant to 10 CFR 50.80 and 50.90.
Notice of the request for approval and
opportunity for a hearing were
published in the Federal Register on
February 28, 2007 (72 FR 9035). No
comments were received. No requests
for hearing or petitions for leave to
intervene were received.
Pursuant to 10 CFR 50.80, no license
for a production or utilization facility,
or any right thereunder, shall be
transferred, directly or indirectly,
through transfer of control of the
license, unless the Commission shall
give its consent in writing. Upon review
of the information in the application
and other information before the
Commission, and relying upon the
representations and agreements
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43669
contained in the application, the NRC
staff has determined that FPLE Point
Beach is qualified to hold the licenses
for Point Beach to the extent now held
by WEPCO regarding its ownership
interest, and is qualified to hold the
operating authority under the licenses
now held by NMC, and the transfer of
the licenses as proposed in the
application is otherwise consistent with
applicable provisions of law,
regulations, and orders issued by the
Commission, subject to the conditions
set forth below. The NRC staff has also
found that the application for the
proposed license amendments complies
with the standards and requirements of
the Atomic Energy Act of 1954, as
amended (the Act), and the
Commission’s rules and regulations set
forth in 10 CFR Chapter I; the facility
will operate in conformity with the
application, the provisions of the Act,
and the rules and regulations of the
Commission; there is reasonable
assurance that the activities authorized
by the proposed license amendments
can be conducted without endangering
the health and safety of the public and
that such activities will be conducted in
compliance with the Commission’s
regulations; the issuance of the
proposed license amendments will not
be inimical to the common defense and
security or to the health and safety of
the public; and issuance of the proposed
amendments will be in accordance with
10 CFR Part 51 of the Commission’s
regulations and all applicable
requirements have been satisfied.
The findings set forth above are
supported by an NRC safety evaluation
dated July 31, 2007.
III.
Accordingly, pursuant to Sections
161b, 161i, 161o and 184 of the Act, 42
U.S.C. Sections 2201(b), 2201(i), 2201(o)
and 2234; and 10 CFR 50.80, It is hereby
ordered that the transfer of the licenses,
as described herein, to FPLE Point
Beach is approved, subject to the
following conditions:
(1) At the time of the closing of the
transfer of the licenses from Wisconsin
Electric Power Company (WEPCO) to
FPLE Point Beach, WEPCO shall
transfer to FPLE Point Beach WEPCO’s
decommissioning funds in an aggregate
minimum value of $200.8 million for
Point Beach, Unit 1 and $189.2 million
for Point Beach, Unit 2. FPLE Point
Beach shall deposit such funds in an
external decommissioning trust fund
established by FPLE Point Beach for
Point Beach Units 1 and 2. The trust
agreement shall be in a form acceptable
to the NRC.
E:\FR\FM\06AUN1.SGM
06AUN1
Agencies
[Federal Register Volume 72, Number 150 (Monday, August 6, 2007)]
[Notices]
[Pages 43666-43669]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-15191]
-----------------------------------------------------------------------
NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-247 and 50-286; License Nos. DPR-26 and DPR-64; EA-07-
189]
In the Matter of Entergy Nuclear Operations, Inc; Indian Point
Nuclear Generating Unit Nos. 2 and 3; 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
On April 23, 2007, the NRC issued to Entergy Nuclear Operations,
Inc. (Entergy) a Notice of Violation (NOV) and Proposed Imposition of
Civil Penalty for a violation involving the failure to meet the
requirements of a Confirmatory Order (EA-05-190) that was issued to
Entergy on January 31, 2006. On January 23, 2007, the NRC granted
Entergy's request, provided in a letter dated January 11, 2007, to
extend the full implementation date until April 15, 2007. The NRC
issued the NOV and Proposed Civil Penalty after Entergy informed the
NRC that the ``radio only activation'' feature of the emergency
notification system (ENS) did not meet its test acceptance criteria,
resulting in the ENS not being fully operable by April 15, 2007, the
date it was required to be operable. Entergy responded to the NOV on
May 23, 2007, and committed to declaring the new ENS operable by August
24, 2007. In its response, Entergy admitted to the violation of the
Confirmatory Order, identified the apparent causes of the violation,
and described corrective actions that were taken or planned to correct
the violation.
Subsequent to the Licensee's May 23, 2007, letter, the NRC held a
public meeting with Entergy officials on July 9, 2007, to clarify
Entergy's actions to comply with the Confirmatory Order, particularly
with respect to ensuring that the new ENS met the applicable Federal
Emergency Management Agency (FEMA) regulations, as well as to ensure
that any specific county needs were identified and addressed prior to
Entergy declaring the new ENS operable.
The NRC has evaluated Entergy's response to the NOV and the
additional information gathered during the July 9, 2007, public
meeting. The NRC has determined that additional actions are needed to
ensure that the new ENS with backup power supply capability is operable
by August 24, 2007, as committed to in Entergy's May 23, 2007 letter.
These actions include: Completing the outstanding requirements
delineated in the aforementioned Confirmatory Order issued January 31,
2006, as modified herein; implementing those measures necessary for
FEMA to accept the new ENS as the primary ENS for alerting the public
by August 24, 2007; and, completing the necessary software and
procedure upgrades and training of county personnel responsible for
actuation of the system.
III
Adequate backup power for the ENS, as required by the Energy Policy
Act of 2005 (Act) (see 42 U.S.C. 2210 et seq.) Section 651(b), 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)
[[Page 43667]]
batteries used for backup power must recharge to at least 80 percent of
their capacity in a period of not more 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 of the Confirmatory
Order.
The requirements needed to implement the foregoing are set forth in
Section IV below. Based on the above, and in consideration of other
communications involving the NRC, FEMA, New York State, the four
counties within the 10 mile Emergency Planning Zone, and Entergy
officials, additional actions are needed to ensure Entergy is in
compliance with the Commission's requirements and that the public
interest will be protected. Therefore, License Nos. DPR-26 and DPR-64
should be modified to require compliance with Section 651(b) of the
Act. Furthermore, pursuant to 10 CFR 2.202, and in consideration of the
ongoing violation of the Confirmatory Order, as well as the prior
enforcement related to such, I find that the significance of compliance
with the Act described above is such that the public interest requires
that this Order be immediately effective.
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 meet all the provisions contained in the
January 31, 2006, Confirmatory Order (see Appendix A of this Order),
except as specifically modified or supplemented herein. With respect to
the requirement to provide and maintain an ENS with backup power supply
capability for the Indian Point Nuclear Generating Unit Nos. 2 and 3
facilities, the new ENS intended to comply with that requirement shall
meet applicable requirements of state and federal authorities such that
it is declared operable and placed into service as the primary system
by August 24, 2007.
II. The Licensee shall provide to NRC within 7 days of this order a
report describing the steps and the expected schedule for completing
each of the steps that the licensee understands are necessary to meet
applicable requirements of state and federal authorities to place the
new ENS system into service as the Primary Notification system. The
report should identify any uncertainties in identification of
requirements or in schedules associated with requirements.
III. Prior to declaring the new ENS operable and using it as the
primary system, the Licensee shall: (a) Obtain FEMA approval that the
system, as installed, meets the design criterion of the approved ENS
Design Report and is in compliance with all applicable FEMA regulations
and guidance; and, (b) complete all necessary software and procedure
upgrades and training of all the four county response organizations,
accounting for the specific training needs identified by the counties,
in the proper use of the new ENS and response to associated alarming
conditions.
IV. The Licensee shall maintain the existing ENS fully available
(including conducting routine maintenance and testing activities) and
establish the necessary procedures and actions to enable its use as a
backup to the new ENS when the new ENS is declared in use as the
primary system, until such time that FEMA grants approval to remove the
existing ENS from service.
The Director, Office of Enforcement, may, in writing, relax or
rescind any of the above conditions upon demonstration by the Licensee
of good cause.
V
In accordance with 10 CFR 2.202, the Licensee must, and any other
person adversely affected by this Order may, submit an answer to this
Order within 20 days of its issuance. In addition, the Licensee and any
other person adversely affected by this Order may request a hearing on
this Order 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 Enforcement, U.S. Nuclear Regulatory Commission,
Washington, DC 20555, and include a statement of good cause for the
extension. Any answer or 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
Enforcement, to the Director, Office of Nuclear Reactor Regulation, and
to the Assistant General Counsel for Materials Litigation and
Enforcement, U.S. Nuclear Regulatory Commission, Washington, DC 20555;
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, if the answer or hearing request is by a person other than the
Licensee. 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(d).
If the 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.
Pursuant to 10 CFR 2.202(c)(2)(i), the Licensee, may, in addition
to demanding a hearing, at the time the answer is filed or sooner, move
the presiding officer to set aside the immediate effectiveness of the
Order on the ground that the Order, including the need for immediate
effectiveness, is not based on adequate evidence but on mere suspicion,
unfounded allegations, or error.
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.
[[Page 43668]]
Dated this 30th day of July 2007.
For the Nuclear Regulatory Commission.
Cynthia A. Carpenter,
Director, Office of Enforcement.
Appendix A--Section IV Excerpt From NRC Confirmatory Order, Dated
January 31, 2006
IV
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
[[Page 43669]]
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.
[FR Doc. E7-15191 Filed 8-3-07; 8:45 am]
BILLING CODE 7590-01-P