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]

Download as PDF 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 VerDate Aug<31>2005 15:52 May 23, 2007 Jkt 211001 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, http://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 VerDate Aug<31>2005 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, http:// 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, http://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, http://
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