Florida Power and Light Company; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing, 29186-29188 [E7-10047]
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29186
Federal Register / Vol. 72, No. 100 / Thursday, May 24, 2007 / Notices
Estimated Number of Respondents:
2000.
Estimated Time per Response: 2
hours.
Estimated Total Annual Burden
Hours: 4000.
Estimated Total Annual Cost: $0.
IV. Request for Comments
Comments are invited on: (1) Whether
the proposed collection of information
is necessary for the proper performance
of the functions of NASA, including
whether the information collected has
practical utility; (2) the accuracy of
NASA’s estimate of the burden
(including hours and cost) of the
proposed collection of information; (3)
ways to enhance the quality, utility, and
clarity of the information to be
collected; and (4) ways to minimize the
burden of the collection of information
on respondents, including automated
collection techniques or the use of other
forms of information technology.
Comments submitted in response to
this notice will be summarized and
included in the request for OMB
approval of this information collection.
They will also become a matter of
public record.
Gary Cox,
Acting Deputy Chief Information Officer.
[FR Doc. E7–9956 Filed 5–23–07; 8:45 am]
BILLING CODE 7510–13–P
NUCLEAR REGULATORY
COMMISSION
[Docket No. 50–250]
rmajette on PROD1PC67 with NOTICES
Florida Power and Light Company;
Notice of Consideration of Issuance of
Amendment to Facility Operating
License, Proposed No Significant
Hazards Consideration Determination,
and Opportunity for a Hearing
The U.S. Nuclear Regulatory
Commission (the Commission) is
considering issuance of an amendment
to Facility Operating License No. DPR–
31, issued to Florida Power and Light
Company (the licensee), for operation of
the Turkey Point Nuclear Plant, Unit 3,
located in Miami-Dade County, Florida.
The proposed amendment would
revise Technical Specifications (TSs) 3/
4.1.3.1, 3/4.1.3.2, and 3/4.1.3.6 to allow
the use of an alternate method of
determining rod position for the control
rods G–5 and M–6, which have
inoperable rod position indicators
(RPIs). The method to be used will
monitor the stationary gripper coils of
G–5 and M–6 Control Rod Drive
Mechanisms until repairs can be
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15:52 May 23, 2007
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conducted, but no later than the next
outage, which is scheduled for fall 2007.
The licensee indicated the need for
the amendment is due to the
unanticipated recent additional failure
of the Turkey Point Unit 3 Analog RPI
for control rod G–5 in Control Rod Bank
A. Additionally, there is a concern that
exercising the movable incore detectors
every 8 hours (90 times per month) to
comply with the compensatory actions
required by the current Action
Statement a. of TS 3.1.3.2 will result in
excessive wear.
Before issuance of the proposed
license amendment, the Commission
will have made findings required by the
Atomic Energy Act of 1954, as amended
(the Act) and the Commission’s
regulations.
The Commission has made a
proposed determination that the
amendment request involves no
significant hazards consideration. Under
the Commission’s regulations in Title 10
of the Code of Federal Regulations (10
CFR), Section 50.92, this means that
operation of the facility in accordance
with the proposed amendment would
not (1) involve a significant increase in
the probability or consequences of an
accident previously evaluated; or (2)
create the possibility of a new or
different kind of accident from any
accident previously evaluated; or (3)
involve a significant reduction in a
margin of safety. As required by 10 CFR
50.91(a), the licensee has provided its
analysis of the issue of no significant
hazards consideration, which is
presented below:
1. Will operation of the facility in
accordance with this proposed change
involve a significant increase in the
probability or consequences of an accident
previously evaluated?
No. The proposed change provides an
alternative method for verifying rod position
of control rod M–6 and G–5. The proposed
change meets the intent of the current
specification in that it ensures verification of
position of the control rod once every eight
(8) hours. The proposed change provides
only an alternative method of monitoring
control rod position and does not change the
assumption or results of any previously
evaluated accident.
Therefore, operation of the facility in
accordance with the proposed amendment
would not involve a significant increase in
the probability or consequences of an
accident previously evaluated.
2. Will operation of the facility in
accordance with this proposed change create
the possibility of a new or different kind of
accident from any accident previously
evaluated?
No. As described above, the proposed
change provides only an alternative method
of determining the position of Unit 3 control
rods M–6 and G–5. No new accident
PO 00000
Frm 00067
Fmt 4703
Sfmt 4703
initiators are introduced by the proposed
alternative manner of performing rod
position verification. The proposed change
does not affect the reactor protection system
or the reactor control system. Hence, no new
failure modes are created that would cause a
new or different kind of accident from any
accident previously evaluated.
Therefore, operation of the facility in
accordance with the proposed amendments
would not create the possibility of a new or
different kind of accident from any accident
previously evaluated.
3. Will operation of the facility in
accordance with this proposed change
involve a significant reduction in a margin of
safety?
No. The bases of Specification 3.1.3.2 state
that the operability of the rod position
indicators is required to determine control
rod positions and thereby ensure compliance
with the control rod alignment and insertion
limits. The proposed change does not alter
the requirement to determine rod position
but provides an alternative method for
determining the position of the affected rods.
As a result, the initial conditions of the
accident analysis are preserved and the
consequences of previously analyzed
accidents are unaffected.
Therefore, operation of the facility in
accordance with the proposed amendments
would not involve a significant reduction in
the margin of safety.
The Commission is seeking public
comments on this proposed
determination. Any comments received
within 30 days after the date of
publication of this notice will be
considered in making any final
determination.
Normally, the Commission will not
issue the amendment until the
expiration of 60 days after the date of
publication of this notice. The
Commission may issue the license
amendment before expiration of the 60day period provided that its final
determination is that the amendment
involves no significant hazards
consideration. In addition, the
Commission may issue the amendment
prior to the expiration of the 30-day
comment period should circumstances
change during the 30-day comment
period such that failure to act in a
timely way would result, for example,
in derating or shutdown of the facility.
Should the Commission take action
prior to the expiration of either the
comment period or the notice period, it
will publish in the Federal Register a
notice of issuance. Should the
Commission make a final No Significant
Hazards Consideration Determination,
any hearing will take place after
issuance. The Commission expects that
the need to take this action will occur
very infrequently.
Written comments may be submitted
by mail to the Chief, Rulemaking,
Directives and Editing Branch, Division
E:\FR\FM\24MYN1.SGM
24MYN1
rmajette on PROD1PC67 with NOTICES
Federal Register / Vol. 72, No. 100 / Thursday, May 24, 2007 / Notices
of Administrative Services, Office of
Administration, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, and should cite the publication
date and page number of this Federal
Register notice. Written comments may
also be delivered to Room 6D59, Two
White Flint North, 11545 Rockville
Pike, Rockville, Maryland, from 7:30
a.m. to 4:15 p.m. Federal workdays.
Documents may be examined, and/or
copied for a fee, at the NRC’s Public
Document Room (PDR), located at One
White Flint North, Public File Area
O1F21, 11555 Rockville Pike (first
floor), Rockville, Maryland.
The filing of requests for hearing and
petitions for leave to intervene is
discussed below.
Within 60 days after the date of
publication of this notice, the licensee
may file a request for a hearing with
respect to issuance of the amendment to
the subject facility operating license and
any person whose interest may be
affected by this proceeding and who
wishes to participate as a party in the
proceeding must file a written request
for a hearing and a petition for leave to
intervene. Requests for a hearing and a
petition for leave to intervene shall be
filed in accordance with the
Commission’s ‘‘Rules of Practice for
Domestic Licensing Proceedings’’ in 10
CFR part 2. Interested persons should
consult a current copy of 10 CFR 2.309,
which is available at the Commission’s
PDR, located at One White Flint North,
Public File Area O1F21, 11555
Rockville Pike (first floor), Rockville,
Maryland. Publicly available records
will be accessible from the Agencywide
Documents Access and Management
System’s (ADAMS) Public Electronic
Reading Room on the Internet at the
NRC Web site, https://www.nrc.gov/
reading-rm/doc-collections/cfr/. If a
request for a hearing or petition for
leave to intervene is filed by the above
date, the Commission or a presiding
officer designated by the Commission or
by the Chief Administrative Judge of the
Atomic Safety and Licensing Board
Panel, will rule on the request and/or
petition; and the Secretary or the Chief
Administrative Judge of the Atomic
Safety and Licensing Board will issue a
notice of a hearing or an appropriate
order.
As required by 10 CFR 2.309, a
petition for leave to intervene shall set
forth with particularity the interest of
the petitioner in the proceeding, and
how that interest may be affected by the
results of the proceeding. The petition
should specifically explain the reasons
why intervention should be permitted
with particular reference to the
following general requirements: (1) The
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15:52 May 23, 2007
Jkt 211001
name, address and telephone number of
the requestor or petitioner; (2) the
nature of the requestor’s/petitioner’s
right under the Act to be made a party
to the proceeding; (3) the nature and
extent of the requestor’s/petitioner’s
property, financial, or other interest in
the proceeding; and (4) the possible
effect of any decision or order which
may be entered in the proceeding on the
requestors/petitioner’s interest. The
petition must also identify the specific
contentions which the petitioner/
requestor seeks to have litigated at the
proceeding.
Each contention must consist of a
specific statement of the issue of law or
fact to be raised or controverted. In
addition, the petitioner/requestor shall
provide a brief explanation of the bases
for the contention and a concise
statement of the alleged facts or expert
opinion which support the contention
and on which the petitioner intends to
rely in proving the contention at the
hearing. The petitioner/requestor must
also provide references to those specific
sources and documents of which the
petitioner is aware and on which the
petitioner intends to rely to establish
those facts or expert opinion. The
petition must include sufficient
information to show that a genuine
dispute exists with the applicant on a
material issue of law or fact.
Contentions shall be limited to matters
within the scope of the amendment
under consideration. The contention
must be one which, if proven, would
entitle the petitioner to relief. A
petitioner/requestor who fails to satisfy
these requirements with respect to at
least one contention will not be
permitted to participate as a party.
Those permitted to intervene become
parties to the proceeding, subject to any
limitations in the order granting leave to
intervene, and have the opportunity to
participate fully in the conduct of the
hearing.
If a hearing is requested, the
Commission will make a final
determination on the issue of no
significant hazards consideration. The
final determination will serve to decide
when the hearing is held. If the final
determination is that the amendment
request involves no significant hazards
consideration, the Commission may
issue the amendment and make it
immediately effective, notwithstanding
the request for a hearing. Any hearing
held would take place after issuance of
the amendment. If the final
determination is that the amendment
request involves a significant hazards
consideration, any hearing held would
take place before the issuance of any
amendment.
PO 00000
Frm 00068
Fmt 4703
Sfmt 4703
29187
Nontimely requests and/or petitions
and contentions will not be entertained
absent a determination by the
Commission or the presiding officer of
the Atomic Safety and Licensing Board
that the petition, request and/or the
contentions should be granted based on
a balancing of the factors specified in 10
CFR 2.309(c)(1)(i)–(viii).
A request for a hearing or a petition
for leave to intervene must be filed by:
(1) First class mail addressed to the
Office of the Secretary of the
Commission, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, Attention: Rulemaking and
Adjudications Staff; (2) courier, express
mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor,
One White Flint North, 11555 Rockville
Pike, Rockville, Maryland 20852,
Attention: Rulemaking and
Adjudications Staff; (3) e-mail
addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission,
HEARINGDOCKET@NRC.GOV; or (4)
facsimile transmission addressed to the
Office of the Secretary, U.S. Nuclear
Regulatory Commission, Washington,
DC, Attention: Rulemakings and
Adjudications Staff at (301) 415–1101,
verification number is (301) 415–1966.
A copy of the request for hearing and
petition for leave to intervene should
also be sent to the Office of the General
Counsel, U.S. Nuclear Regulatory
Commission, Washington, DC 20555–
0001, and it is requested that copies be
transmitted either by means of facsimile
transmission to 301–415–3725 or by email to OGCMailCenter@nrc.gov. A copy
of the request for hearing and petition
for leave to intervene should also be
sent to M. S. Ross, Managing Attorney,
Florida Power & Light Company, P.O.
Box 14000, Juno Beach, FL 33408–0420,
attorney for the licensee.
For further details with respect to this
action, see the application for
amendment dated May 17, 2007, which
is available for public inspection at the
Commission’s PDR, located at One
White Flint North, File Public Area O1
F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available
records will be accessible from the
Agencywide Documents Access and
Management System’s (ADAMS) Public
Electronic Reading Room on the Internet
at the NRC Web site, https://
www.nrc.gov/reading-rm/adams.html.
Persons who do not have access to
ADAMS or who encounter problems in
accessing the documents located in
ADAMS, should contact the NRC PDR
Reference staff by telephone at 1–800–
397–4209, 301–415–4737, or by e-mail
to pdr@nrc.gov.
E:\FR\FM\24MYN1.SGM
24MYN1
29188
Federal Register / Vol. 72, No. 100 / Thursday, May 24, 2007 / Notices
Dated at Rockville, Maryland, this 17th day
of May 2007.
Brenda L. Mozafari,
Senior Project Manager, Plant Licensing
Branch II–2, Division of Operating Reactor
Licensing, Office of Nuclear Reactor
Regulation.
[FR Doc. E7–10047 Filed 5–23–07; 8:45 am]
BILLING CODE 7590–01–P
RAILROAD RETIREMENT BOARD
rmajette on PROD1PC67 with NOTICES
Agency Forms Submitted for OMB
Review, Request for Comments
Summary: In accordance with the
Paperwork Reduction Act of 1995 (44
U.S.C. Chapter 35), the Railroad
Retirement Board (RRB) is forwarding
an Information Collection Request (ICR)
to the Office of Information and
Regulatory Affairs (OIRA), Office of
Management and Budget (OMB) to
request a revision to the following
collection of information: 3220–0198,
Request for Internet Services. Our ICR
describes the information we seek to
collect from the public. Review and
approval by OIRA ensures that we
impose appropriate paperwork burdens.
The RRB uses a Personal
Identification Number (PIN)/Password
system that allows RRB customers to
conduct business with the agency
electronically. As part of the system, the
RRB collects information needed to
establish a unique PIN/Password that
allows customer access to RRB Internetbased services. The information
collected is matched against records of
the railroad employee that are
maintained by the RRB. If the
information is verified, the request is
approved and the RRB mails a Password
Request Code (PRC) to the requestor. If
the information provided cannot be
verified, the requestor is advised to
contact the nearest field office of the
RRB to resolve the discrepancy. Once a
PRC is obtained from the RRB, the
requestor can apply for a PIN/Password
online. Once the PIN/Password has been
established, the requestor has access to
RRB Internet-based services. The RRB
estimates that approximately 14,040
requests for PRC’s and 14,040 PIN/
Passwords are established annually and
that it takes 5 minutes per response to
secure a PRC and 1.5 minutes to
establish a PIN/Password. Two
responses are requested of each
respondent and completion is
voluntary.
However, the RRB will be unable to
provide a PRC or allow a requestor to
establish a PIN/Password (thereby
denying system access), if the requests
are not completed. The RRB proposes
VerDate Aug<31>2005
15:52 May 23, 2007
Jkt 211001
non-burden impacting, editorial changes
to the PRC and PIN/Password screens.
The RRB invites comments on the
proposed collection of information to
determine (1) the practical utility of the
collection; (2) the accuracy of the
estimated burden of the collection; (3)
ways to enhance the quality, utility and
clarity of the information that is the
subject of collection; and (4) ways to
minimize the burden of collections on
respondents, including the use of
automated collection techniques or
other forms of information technology.
Comments to RRB or OIRA must contain
the OMB control number of the ICR. For
proper consideration of your comments,
it is best if RRB and OIRA receive them
within 30 days of publication date.
Previous Requests for Comments: The
RRB has already published the initial
60-day notice (72 FR 13828 on March
23, 2007) required by 44 U.S.C.
3506(c)(2). That request elicited no
comments.
Information Collection Request (ICR)
Title: Request for Internet Services.
OMB Control Number: 3220–0198.
Form(s) submitted: N/A.
Type of request: Revision of a
currently approved collection.
Affected public: Individuals or
households.
Abstract: The Railroad Retirement
Board collects information needed to
provide customers with the ability to
request a Password Request Code and
subsequently, to establish an individual
PIN/Password, the initial steps in
providing the option of conducting
transactions with the RRB on a routine
basis through the Internet.
Changes Proposed: The RRB proposes
minor, non-burden impacting, editorial
changes to the PRC and Pin/Password
screens.
The burden estimate for the ICR is as
follows:
Estimated annual number of
respondents: 14,040.
Total annual responses: 28,080.
Total annual reporting hours: 1,521.
Additional Information or Comments:
Copies of the screens and supporting
documents can be obtained by
contacting Charles Mierzwa, the agency
clearance officer, at (312–751–3363) or
Charles.Mierzwa@rrb.gov.
Comments regarding the information
collection should be addressed to
Ronald J. Hodapp, Railroad Retirement
Board, 844 North Rush Street, Chicago,
Illinois, 60611–2092 or
Ronald.Hodapp@rrb.gov and to the
OMB Desk Officer for the RRB, at the
Office of Management and Budget,
PO 00000
Frm 00069
Fmt 4703
Sfmt 4703
Room 10230, New Executive Office
Building, Washington, DC 20503.
Charles Mierzwa,
Clearance Officer.
[FR Doc. E7–10021 Filed 5–23–07; 8:45 am]
BILLING CODE 7905–01–P
RAILROAD RETIREMENT BOARD
Agency Forms Submitted for OMB
Review, Request for Comments
Summary: In accordance with the
Paperwork Reduction Act of 1995 (44
U.S.C. Chapter 35), the Railroad
Retirement Board (RRB) is forwarding
an Information Collection Request (ICR)
to the Office of Information and
Regulatory Affairs (OIRA), Office of
Management and Budget (OMB) to
request an extension of the following
collection of information: 3220–0070,
Employer Service and Compensation
Reports.
Section 2(c) of the Railroad
Unemployment Insurance Act (RUIA)
specifies the maximum normal
unemployment and sickness benefits
that may be paid in a benefit year.
Section 2(c) further provides for
extended benefits for certain employees
and for beginning a benefit year early for
other employees. The conditions for
these actions are prescribed in 20 CFR
part 302.
All information about creditable
railroad service and compensation
needed by the RRB to administer
Section 2(c) is not always available from
annual reports filed by railroad
employers with the RRB (OMB 3220–
0008). When this occurs, the RRB must
obtain supplemental information about
service and compensation. The RRB
utilizes Form(s) UI–41, Supplemental
Report of Service and Compensation,
and UI–41a, Supplemental Report of
Compensation, to obtain the necessary
information.
Our ICR describes the information we
seek to collect from the public.
Completion of the forms is mandatory.
One response is required (per
individual) from a respondent. Review
and approval by OIRA ensures that we
impose appropriate paperwork burdens.
The RRB invites comments on the
proposed collection of information to
determine (1) the practical utility of the
collection; (2) the accuracy of the
estimated burden of the collection; (3)
ways to enhance the quality, utility and
clarity of the information that is the
subject of collection; and (4) ways to
minimize the burden of collections on
respondents, including the use of
automated collection techniques or
other forms of information technology.
E:\FR\FM\24MYN1.SGM
24MYN1
]]>Agencies
[Federal Register Volume 72, Number 100 (Thursday, May 24, 2007)]
[Notices]
[Pages 29186-29188]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-10047]
=======================================================================
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-250]
Florida Power and Light Company; Notice of Consideration of
Issuance of Amendment to Facility Operating License, Proposed No
Significant Hazards Consideration Determination, and Opportunity for a
Hearing
The U.S. Nuclear Regulatory Commission (the Commission) is
considering issuance of an amendment to Facility Operating License No.
DPR-31, issued to Florida Power and Light Company (the licensee), for
operation of the Turkey Point Nuclear Plant, Unit 3, located in Miami-
Dade County, Florida.
The proposed amendment would revise Technical Specifications (TSs)
3/4.1.3.1, 3/4.1.3.2, and 3/4.1.3.6 to allow the use of an alternate
method of determining rod position for the control rods G-5 and M-6,
which have inoperable rod position indicators (RPIs). The method to be
used will monitor the stationary gripper coils of G-5 and M-6 Control
Rod Drive Mechanisms until repairs can be conducted, but no later than
the next outage, which is scheduled for fall 2007.
The licensee indicated the need for the amendment is due to the
unanticipated recent additional failure of the Turkey Point Unit 3
Analog RPI for control rod G-5 in Control Rod Bank A. Additionally,
there is a concern that exercising the movable incore detectors every 8
hours (90 times per month) to comply with the compensatory actions
required by the current Action Statement a. of TS 3.1.3.2 will result
in excessive wear.
Before issuance of the proposed license amendment, the Commission
will have made findings required by the Atomic Energy Act of 1954, as
amended (the Act) and the Commission's regulations.
The Commission has made a proposed determination that the amendment
request involves no significant hazards consideration. Under the
Commission's regulations in Title 10 of the Code of Federal Regulations
(10 CFR), Section 50.92, this means that operation of the facility in
accordance with the proposed amendment would not (1) involve a
significant increase in the probability or consequences of an accident
previously evaluated; or (2) create the possibility of a new or
different kind of accident from any accident previously evaluated; or
(3) involve a significant reduction in a margin of safety. As required
by 10 CFR 50.91(a), the licensee has provided its analysis of the issue
of no significant hazards consideration, which is presented below:
1. Will operation of the facility in accordance with this
proposed change involve a significant increase in the probability or
consequences of an accident previously evaluated?
No. The proposed change provides an alternative method for
verifying rod position of control rod M-6 and G-5. The proposed
change meets the intent of the current specification in that it
ensures verification of position of the control rod once every eight
(8) hours. The proposed change provides only an alternative method
of monitoring control rod position and does not change the
assumption or results of any previously evaluated accident.
Therefore, operation of the facility in accordance with the
proposed amendment would not involve a significant increase in the
probability or consequences of an accident previously evaluated.
2. Will operation of the facility in accordance with this
proposed change create the possibility of a new or different kind of
accident from any accident previously evaluated?
No. As described above, the proposed change provides only an
alternative method of determining the position of Unit 3 control
rods M-6 and G-5. No new accident initiators are introduced by the
proposed alternative manner of performing rod position verification.
The proposed change does not affect the reactor protection system or
the reactor control system. Hence, no new failure modes are created
that would cause a new or different kind of accident from any
accident previously evaluated.
Therefore, operation of the facility in accordance with the
proposed amendments would not create the possibility of a new or
different kind of accident from any accident previously evaluated.
3. Will operation of the facility in accordance with this
proposed change involve a significant reduction in a margin of
safety?
No. The bases of Specification 3.1.3.2 state that the
operability of the rod position indicators is required to determine
control rod positions and thereby ensure compliance with the control
rod alignment and insertion limits. The proposed change does not
alter the requirement to determine rod position but provides an
alternative method for determining the position of the affected
rods. As a result, the initial conditions of the accident analysis
are preserved and the consequences of previously analyzed accidents
are unaffected.
Therefore, operation of the facility in accordance with the
proposed amendments would not involve a significant reduction in the
margin of safety.
The Commission is seeking public comments on this proposed
determination. Any comments received within 30 days after the date of
publication of this notice will be considered in making any final
determination.
Normally, the Commission will not issue the amendment until the
expiration of 60 days after the date of publication of this notice. The
Commission may issue the license amendment before expiration of the 60-
day period provided that its final determination is that the amendment
involves no significant hazards consideration. In addition, the
Commission may issue the amendment prior to the expiration of the 30-
day comment period should circumstances change during the 30-day
comment period such that failure to act in a timely way would result,
for example, in derating or shutdown of the facility. Should the
Commission take action prior to the expiration of either the comment
period or the notice period, it will publish in the Federal Register a
notice of issuance. Should the Commission make a final No Significant
Hazards Consideration Determination, any hearing will take place after
issuance. The Commission expects that the need to take this action will
occur very infrequently.
Written comments may be submitted by mail to the Chief, Rulemaking,
Directives and Editing Branch, Division
[[Page 29187]]
of Administrative Services, Office of Administration, U.S. Nuclear
Regulatory Commission, Washington, DC 20555-0001, and should cite the
publication date and page number of this Federal Register notice.
Written comments may also be delivered to Room 6D59, Two White Flint
North, 11545 Rockville Pike, Rockville, Maryland, from 7:30 a.m. to
4:15 p.m. Federal workdays. Documents may be examined, and/or copied
for a fee, at the NRC's Public Document Room (PDR), located at One
White Flint North, Public File Area O1F21, 11555 Rockville Pike (first
floor), Rockville, Maryland.
The filing of requests for hearing and petitions for leave to
intervene is discussed below.
Within 60 days after the date of publication of this notice, the
licensee may file a request for a hearing with respect to issuance of
the amendment to the subject facility operating license and any person
whose interest may be affected by this proceeding and who wishes to
participate as a party in the proceeding must file a written request
for a hearing and a petition for leave to intervene. Requests for a
hearing and a petition for leave to intervene shall be filed in
accordance with the Commission's ``Rules of Practice for Domestic
Licensing Proceedings'' in 10 CFR part 2. Interested persons should
consult a current copy of 10 CFR 2.309, which is available at the
Commission's PDR, located at One White Flint North, Public File Area
O1F21, 11555 Rockville Pike (first floor), Rockville, Maryland.
Publicly available records will be accessible from the Agencywide
Documents Access and Management System's (ADAMS) Public Electronic
Reading Room on the Internet at the NRC Web site, https://www.nrc.gov/
reading-rm/doc-collections/cfr/. If a request for a hearing or petition
for leave to intervene is filed by the above date, the Commission or a
presiding officer designated by the Commission or by the Chief
Administrative Judge of the Atomic Safety and Licensing Board Panel,
will rule on the request and/or petition; and the Secretary or the
Chief Administrative Judge of the Atomic Safety and Licensing Board
will issue a notice of a hearing or an appropriate order.
As required by 10 CFR 2.309, a petition for leave to intervene
shall set forth with particularity the interest of the petitioner in
the proceeding, and how that interest may be affected by the results of
the proceeding. The petition should specifically explain the reasons
why intervention should be permitted with particular reference to the
following general requirements: (1) The name, address and telephone
number of the requestor or petitioner; (2) the nature of the
requestor's/petitioner's right under the Act to be made a party to the
proceeding; (3) the nature and extent of the requestor's/petitioner's
property, financial, or other interest in the proceeding; and (4) the
possible effect of any decision or order which may be entered in the
proceeding on the requestors/petitioner's interest. The petition must
also identify the specific contentions which the petitioner/requestor
seeks to have litigated at the proceeding.
Each contention must consist of a specific statement of the issue
of law or fact to be raised or controverted. In addition, the
petitioner/requestor shall provide a brief explanation of the bases for
the contention and a concise statement of the alleged facts or expert
opinion which support the contention and on which the petitioner
intends to rely in proving the contention at the hearing. The
petitioner/requestor must also provide references to those specific
sources and documents of which the petitioner is aware and on which the
petitioner intends to rely to establish those facts or expert opinion.
The petition must include sufficient information to show that a genuine
dispute exists with the applicant on a material issue of law or fact.
Contentions shall be limited to matters within the scope of the
amendment under consideration. The contention must be one which, if
proven, would entitle the petitioner to relief. A petitioner/requestor
who fails to satisfy these requirements with respect to at least one
contention will not be permitted to participate as a party.
Those permitted to intervene become parties to the proceeding,
subject to any limitations in the order granting leave to intervene,
and have the opportunity to participate fully in the conduct of the
hearing.
If a hearing is requested, the Commission will make a final
determination on the issue of no significant hazards consideration. The
final determination will serve to decide when the hearing is held. If
the final determination is that the amendment request involves no
significant hazards consideration, the Commission may issue the
amendment and make it immediately effective, notwithstanding the
request for a hearing. Any hearing held would take place after issuance
of the amendment. If the final determination is that the amendment
request involves a significant hazards consideration, any hearing held
would take place before the issuance of any amendment.
Nontimely requests and/or petitions and contentions will not be
entertained absent a determination by the Commission or the presiding
officer of the Atomic Safety and Licensing Board that the petition,
request and/or the contentions should be granted based on a balancing
of the factors specified in 10 CFR 2.309(c)(1)(i)-(viii).
A request for a hearing or a petition for leave to intervene must
be filed by: (1) First class mail addressed to the Office of the
Secretary of the Commission, U.S. Nuclear Regulatory Commission,
Washington, DC 20555-0001, Attention: Rulemaking and Adjudications
Staff; (2) courier, express mail, and expedited delivery services:
Office of the Secretary, Sixteenth Floor, One White Flint North, 11555
Rockville Pike, Rockville, Maryland 20852, Attention: Rulemaking and
Adjudications Staff; (3) e-mail addressed to the Office of the
Secretary, U.S. Nuclear Regulatory Commission, HEARINGDOCKET@NRC.GOV;
or (4) facsimile transmission addressed to the Office of the Secretary,
U.S. Nuclear Regulatory Commission, Washington, DC, Attention:
Rulemakings and Adjudications Staff at (301) 415-1101, verification
number is (301) 415-1966. A copy of the request for hearing and
petition for leave to intervene should also be sent to the Office of
the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC
20555-0001, and it is requested that copies be transmitted either by
means of facsimile transmission to 301-415-3725 or by e-mail to
OGCMailCenter@nrc.gov. A copy of the request for hearing and petition
for leave to intervene should also be sent to M. S. Ross, Managing
Attorney, Florida Power & Light Company, P.O. Box 14000, Juno Beach, FL
33408-0420, attorney for the licensee.
For further details with respect to this action, see the
application for amendment dated May 17, 2007, which is available for
public inspection at the Commission's PDR, located at One White Flint
North, File Public Area O1 F21, 11555 Rockville Pike (first floor),
Rockville, Maryland. Publicly available records will be accessible from
the Agencywide Documents Access and Management System's (ADAMS) Public
Electronic Reading Room on the Internet at the NRC Web site, https://
www.nrc.gov/reading-rm/adams.html. Persons who do not have access to
ADAMS or who encounter problems in accessing the documents located in
ADAMS, should contact the NRC PDR Reference staff by telephone at 1-
800-397-4209, 301-415-4737, or by e-mail to pdr@nrc.gov.
[[Page 29188]]
Dated at Rockville, Maryland, this 17th day of May 2007.
Brenda L. Mozafari,
Senior Project Manager, Plant Licensing Branch II-2, Division of
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E7-10047 Filed 5-23-07; 8:45 am]
BILLING CODE 7590-01-P
