Entergy Nuclear Operations, Inc.; Notice of Consideration of Issuance of Amendment to Renewed Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing, 37544-37546 [E7-13360]

Download as PDF 37544 Federal Register / Vol. 72, No. 131 / Tuesday, July 10, 2007 / Notices SUPPLEMENTARY INFORMATION: NUCLEAR REGULATORY COMMISSION I. Abstract The NASA Explorer Schools (NES) seeks a clearance to collect data from educators to determine eligibility and selection of schools to participate in their three year project. To lessen the impact on educators who will complete the project application, the application period must be open during the times when they are less likely to be needed in the classroom (e.g., summer break) and can obtain any required school board approvals. II. Method of Collection NASA will utilize a Web-based online form to collect this information. III. Data Title: NASA Explorer Schools Project Application. OMB Number: 2700–0130. Type of review: Regular. Affected Public: Individuals or households. Estimated Number of Respondents: 130. Estimated Time Per Response: 1 hour. Estimated Total Annual Burden Hours: 130. Estimated Total Annual Cost: $0. IV. Request for Comments jlentini on PROD1PC65 with NOTICES 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. E7–13281 Filed 7–9–07; 8:45 am] BILLING CODE 7510–13–P VerDate Aug<31>2005 16:17 Jul 09, 2007 Jkt 211001 [Docket No. 50–255] Entergy Nuclear Operations, Inc.; Notice of Consideration of Issuance of Amendment to Renewed 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 Renewed Facility Operating License No. DPR–20 issued to Entergy Nuclear Operations, Inc. (the licensee) for operation of the Palisades Nuclear Plant (PNP) located in Van Buren County, Michigan. The proposed amendment would revise Technical Specification (TS) 3.5.5, ‘‘Trisodium Phosphate,’’ and the associated surveillance requirements by replacing the containment sump buffering agent, trisodium phosphate (TSP), with sodium tetraborate decahydrate (STB). In particular, the proposed amendment would revise the TS Limiting Condition for Operation (LCO) 3.5.5, with a new weight requirement for STB. 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. Does the proposed amendment involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. The proposed amendment does not involve a significant increase in the probability of an accident previously evaluated because the containment buffering agent is not an PO 00000 Frm 00041 Fmt 4703 Sfmt 4703 initiator of any analyzed accident. The proposed change does not impact any failure modes that could lead to an accident. The proposed amendment does not involve a significant increase in the consequences of an accident previously evaluated. The buffering agent in containment is designed to buffer the acids expected to be produced after a loss of coolant accident (LOCA) and is credited in the radiological analysis for iodine retention. The proposed change of replacing TSP with STB in containment results in the radiological consequences remaining under 10 CFR 100 limits and General Design Criterion (GDC) ¥19 limits. 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. Does the proposed amendment create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. STB is a passive component that is proposed to be used at PNP as a buffering agent to increase the pH of the initially acidic post-LOCA containment water to a more neutral pH. Changing the proposed buffering agent from TSP to STB does not constitute an accident initiator or create a new or different kind of accident previously analyzed. The proposed amendment does not involve operation of any required systems, structures or components (SSCs) in a manner or configuration different from those previously recognized or evaluated. No new failure mechanisms will be introduced by the changes being requested. Therefore, the proposed amendment does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed amendment involve a significant reduction in a margin of safety? Response: No. The proposed amendment does not involve a significant reduction in a margin of safety. The proposed amendment of changing the buffering agent from TSP to STB results in equivalent control of maintaining sump pH at 7.0 or greater, thereby controlling containment atmosphere iodine and ensuring the radiological consequences of a MHA [Maximum Hypothetical Accident] are within regulatory limits. The use of STB also reduces the present potential for exacerbating sump screen blockage due to a potential chemical interaction between TSP and certain calcium sources used in containment to form calcium phosphate. This proposed amendment removes this phosphate source from containment, thereby reducing the amount of precipitate that may be formed in a postulated LOCA. The buffer change would minimize the potential chemical effects and should enhance the ability of the emergency core cooling system to perform the postaccident mitigating functions. Therefore, the proposed amendment does not involve a significant reduction in the margin of safety. E:\FR\FM\10JYN1.SGM 10JYN1 jlentini on PROD1PC65 with NOTICES Federal Register / Vol. 72, No. 131 / Tuesday, July 10, 2007 / Notices The NRC staff has reviewed the licensee’s analysis and, based on this review, it appears that the three standards of 10 CFR 50.92(c) are satisfied. Therefore, the NRC staff proposes to determine that the amendment request involves no significant hazards consideration. 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 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 VerDate Aug<31>2005 16:17 Jul 09, 2007 Jkt 211001 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 requestor’s/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 PO 00000 Frm 00042 Fmt 4703 Sfmt 4703 37545 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. Non-timely 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(a)(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 E:\FR\FM\10JYN1.SGM 10JYN1 37546 Federal Register / Vol. 72, No. 131 / Tuesday, July 10, 2007 / Notices 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 Mr. William Dennis, Assistant General Counsel, Entergy Nuclear Operations, Inc., 440 Hamilton Ave., White Plains, NY 10601, the attorney for the licensee. For further details with respect to this action, see the application for amendment dated June 29, 2007, which is available for public inspection at the Commission’s PDR, located at One White Flint North, File Public 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/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. Dated at Rockville, Maryland, this 3rd day of July 2007. For the Nuclear Regulatory Commission. Peter S. Tam, Senior Project Manager, Plant Licensing Branch III–1, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E7–13360 Filed 7–9–07; 8:45 am] [Docket Nos. 50–498 and 50–499] [Docket No. 50–250] Florida Power and Light Company; Notice of Withdrawal of Application for Amendment to Facility Operating License The U.S. Nuclear Regulatory Commission (the Commission) has granted the request of Florida Power and Light Company (the licensee) to withdraw its May 17, 2007, application for proposed amendment to Facility Operating License No. DPR–31 for the Turkey Point Plant, Unit 3, located in Dade County, Florida. The proposed amendment would have revised the Technical Specifications to allow the use of an alternate method of determining rod position for control rods M–6 and G–5 with inoperable Analog Rod Position Indicators. The Commission had previously issued a Notice of Consideration of Issuance of Amendment published in the Federal Register on May 24, 2007 (72 FR 29186). However, by letter dated June 13, 2007, the licensee withdrew the proposed change. For further details with respect to this action, see the application for amendment dated May 17, 2007, and the licensee’s letter dated June 13, 2007, which withdrew the application for license amendment. 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 O1 F21, 11555 Rockville Pike (first floor), Rockville, Maryland. Publicly available records will be accessible electronically from the Agencywide Documents Access and Management Systems (ADAMS) Public Electronic Reading Room on the internet at the NRC Web site, http:// www.nrc.gov/reading-rm.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, or 301–415–4737 or by e-mail to: pdr@nrc.gov. BILLING CODE 7590–01–P VerDate Aug<31>2005 16:17 Jul 09, 2007 NUCLEAR REGULATORY COMMISSION Dated at Rockville, Maryland, this 29th day of June 2007. For the Nuclear Regulatory Commission. Brenda Mozafari, Senior Project Manager, Plant Licensing Branch II–2, Division of Operating Reactor Licensing, Office of Nuclear Reactor Regulation. [FR Doc. E7–13357 Filed 7–9–07; 8:45 am] BILLING CODE 7590–01–P jlentini on PROD1PC65 with NOTICES NUCLEAR REGULATORY COMMISSION Jkt 211001 PO 00000 Frm 00043 Fmt 4703 Sfmt 4703 STP Nuclear Operating Company; South Texas Project, Units 1 and 2; Notice of Consideration of Approval of Application Regarding Proposed Indirect Transfer of Control of Facility Operating Licenses, and Opportunity for a Hearing The U.S. Nuclear Regulatory Commission (the Commission, NRC) is considering the issuance of an order under 10 CFR 50.80 approving the indirect transfer of control of Facility Operating Licenses, numbered NPF–76 and NPF–80, for the South Texas Project (STP), Units 1 and 2, respectively, to the extent owned by NRG South Texas LP (NRG South Texas).1 STP Nuclear Operating Company (STPNOC), acting on behalf of itself and NRG South Texas and its corporate parent, NRG Energy Inc. (NRG Energy), requests that the NRC consent to the indirect transfer of control of STP, Units 1 and 2, licenses to the extent owned by NRG South Texas. NRG South Texas owns 44 percent of STP, Units 1 and 2. NRG Energy plans to reorganize its corporate structure by creating a new publicly-held holding company (NRG HoldCo) that will become the parent company for NRG Energy and its subsidiaries. NRG Energy is seeking NRC consent to the indirect transfer of control of its licenses that result from the establishment of NRG HoldCo. In addition to its 44 percent undivided ownership interest in STP, Units 1 and 2, NRG South Texas holds a corresponding interest in STPNOC, a not-for-profit Texas corporation, which is the licensed operator of STP, Units 1 and 2. Thus, the indirect transfer of control of NRG South Texas also results in the indirect transfer of this interest in STPNOC. STPNOC states that this is not a controlling interest in STPNOC and, therefore, there will be no indirect transfer of STPNOC’s licenses to operate on behalf of the owners. The applicant indicates that if the NRC concludes that indirect transfer of control of NRG South Texas’ interest in STPNOC requires prior NRC consent, it requests such consent. According to an application for approval filed by STPNOC, in connection with the NRG Energy plans to reorganize its corporate structure by operating a new publicly-held holding 1 On June 29, 2007, the NRC granted an amendment request changing the name of one of the licensees from Texas Genco, LP, to NRG South Texas LP. E:\FR\FM\10JYN1.SGM 10JYN1

Agencies

[Federal Register Volume 72, Number 131 (Tuesday, July 10, 2007)]
[Notices]
[Pages 37544-37546]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E7-13360]


=======================================================================
-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Docket No. 50-255]


Entergy Nuclear Operations, Inc.; Notice of Consideration of 
Issuance of Amendment to Renewed 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 Renewed Facility Operating 
License No. DPR-20 issued to Entergy Nuclear Operations, Inc. (the 
licensee) for operation of the Palisades Nuclear Plant (PNP) located in 
Van Buren County, Michigan.
    The proposed amendment would revise Technical Specification (TS) 
3.5.5, ``Trisodium Phosphate,'' and the associated surveillance 
requirements by replacing the containment sump buffering agent, 
trisodium phosphate (TSP), with sodium tetraborate decahydrate (STB). 
In particular, the proposed amendment would revise the TS Limiting 
Condition for Operation (LCO) 3.5.5, with a new weight requirement for 
STB.
    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. Does the proposed amendment involve a significant increase in 
the probability or consequences of an accident previously evaluated?
    Response: No.
    The proposed amendment does not involve a significant increase 
in the probability of an accident previously evaluated because the 
containment buffering agent is not an initiator of any analyzed 
accident. The proposed change does not impact any failure modes that 
could lead to an accident.
    The proposed amendment does not involve a significant increase 
in the consequences of an accident previously evaluated. The 
buffering agent in containment is designed to buffer the acids 
expected to be produced after a loss of coolant accident (LOCA) and 
is credited in the radiological analysis for iodine retention. The 
proposed change of replacing TSP with STB in containment results in 
the radiological consequences remaining under 10 CFR 100 limits and 
General Design Criterion (GDC) -19 limits.
    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. Does the proposed amendment create the possibility of a new 
or different kind of accident from any accident previously 
evaluated?
    Response: No.
    The proposed amendment does not create the possibility of a new 
or different kind of accident from any accident previously 
evaluated. STB is a passive component that is proposed to be used at 
PNP as a buffering agent to increase the pH of the initially acidic 
post-LOCA containment water to a more neutral pH.
    Changing the proposed buffering agent from TSP to STB does not 
constitute an accident initiator or create a new or different kind 
of accident previously analyzed. The proposed amendment does not 
involve operation of any required systems, structures or components 
(SSCs) in a manner or configuration different from those previously 
recognized or evaluated. No new failure mechanisms will be 
introduced by the changes being requested.
    Therefore, the proposed amendment does not create the 
possibility of a new or different kind of accident from any accident 
previously evaluated.
    3. Does the proposed amendment involve a significant reduction 
in a margin of safety?
    Response: No.
    The proposed amendment does not involve a significant reduction 
in a margin of safety. The proposed amendment of changing the 
buffering agent from TSP to STB results in equivalent control of 
maintaining sump pH at 7.0 or greater, thereby controlling 
containment atmosphere iodine and ensuring the radiological 
consequences of a MHA [Maximum Hypothetical Accident] are within 
regulatory limits. The use of STB also reduces the present potential 
for exacerbating sump screen blockage due to a potential chemical 
interaction between TSP and certain calcium sources used in 
containment to form calcium phosphate. This proposed amendment 
removes this phosphate source from containment, thereby reducing the 
amount of precipitate that may be formed in a postulated LOCA. The 
buffer change would minimize the potential chemical effects and 
should enhance the ability of the emergency core cooling system to 
perform the post-accident mitigating functions.
    Therefore, the proposed amendment does not involve a significant 
reduction in the margin of safety.


[[Page 37545]]


    The NRC staff has reviewed the licensee's analysis and, based on 
this review, it appears that the three standards of 10 CFR 50.92(c) are 
satisfied. Therefore, the NRC staff proposes to determine that the 
amendment request involves no significant hazards consideration.
    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 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 requestor's/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.
    Non-timely 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(a)(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

[[Page 37546]]

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 Mr. William Dennis, Assistant General Counsel, Entergy Nuclear 
Operations, Inc., 440 Hamilton Ave., White Plains, NY 10601, the 
attorney for the licensee.
    For further details with respect to this action, see the 
application for amendment dated June 29, 2007, which is available for 
public inspection at the Commission's PDR, located at One White Flint 
North, File Public 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/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.

    Dated at Rockville, Maryland, this 3rd day of July 2007.

    For the Nuclear Regulatory Commission.
Peter S. Tam,
Senior Project Manager, Plant Licensing Branch III-1, Division of 
Operating Reactor Licensing, Office of Nuclear Reactor Regulation.
[FR Doc. E7-13360 Filed 7-9-07; 8:45 am]
BILLING CODE 7590-01-P