Southern California Edison Company; Notice of Consideration of Issuance of Amendment to Facility Operating License, Proposed No Significant Hazards Consideration Determination, and Opportunity for a Hearing, 34506-34508 [E5-3065]

Download as PDF 34506 Federal Register / Vol. 70, No. 113 / Tuesday, June 14, 2005 / Notices days after the effective date of such change. 4. Who is required or asked to report: Any physician, veterinarian in the practice of veterinary medicine, clinical laboratory or hospital which desires a general license to receive, acquire, possess, transfer, or use specified units of byproduct material in certain in vitro clinical or laboratory tests. 5. The estimated number of annual respondents: 364 (104 NRC licensees and 260 Agreement State licensees). 6. The number of hours needed annually to complete the requirement or request: 42 hours (12 hours NRC licensees and 30 hours Agreement State licensees). 7. Abstract: Section 31.11 of 10 CFR establishes a general license authorizing any physician, clinical laboratory, veterinarian in the practice of veterinary medicine, or hospital to possess certain small quantities of byproduct material for in vitro clinical or laboratory tests not involving the internal or external administration of the byproduct material or the radiation therefrom to human beings or animals. Possession of byproduct material under 10 CFR 31.11 is not authorized until the physician, clinical laboratory, veterinarian in the practice of veterinary medicine, or hospital has filed NRC Form 483 and received from the Commission a validated copy of NRC Form 483 with a registration number. Submit, by August 15, 2005, comments that address the following questions: 1. Is the proposed collection of information necessary for the NRC to properly perform its functions? Does the information have practical utility? 2. Is the burden estimate accurate? 3. Is there a way to enhance the quality, utility, and clarity of the information to be collected? 4. How can the burden of the information collection be minimized, including the use of automated collection techniques or other forms of information technology? A copy of the draft supporting statement may be viewed free of charge at the NRC Public Document Room, One White Flint North, 11555 Rockville Pike, Room O–1 F21, Rockville, MD 20852. OMB clearance requests are available at the NRC worldwide Web site: http://www.nrc.gov/public-involve/ doc-comment/omb/index.html. The document will be available on the NRC home page site for 60 days after the signature date of this notice. Comments and questions about the information collection requirements may be directed to the NRC Clearance Officer, Brenda Jo. Shelton, U.S. Nuclear VerDate jul<14>2003 20:14 Jun 13, 2005 Jkt 205001 Regulatory Commission, T–5 F53, Washington, DC 20555–0001, by telephone at 301–415–7233, or by Internet electronic mail to INFOCOLLECTS@NRC.GOV. Dated at Rockville, Maryland, this 8th day of June 2005. For the Nuclear Regulatory Commission. Brenda Jo. Shelton, NRC Clearance Officer, Office of Information Services. [FR Doc. E5–3064 Filed 6–13–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION [Docket Nos. 50–361 and 50–362] Southern California Edison 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 Nos. NPF– 10 and NPF–15, issued to Southern California Edison Company (SCE or the licensee), for operation of the San Onofre Nuclear Generating Station (SONGS), Units 2 and 3 located in San Diego County, California. The proposed amendment would lower the allowable values for dropout and pickup of the degraded voltage function. The amendment request was submitted on May 27, 2005, on an exigent basis because the need for a license amendment to change the degraded voltage function was not recognized by the licensee or the NRC staff until recently, and the licensee requests approval of the proposed amendment by July 1, 2005, to allow implementation of the amendment before the expected high summer load period. 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. Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under exigent circumstances, the NRC staff must determine that the amendment request involves no significant hazards consideration. Under the Commission’s regulations in 10 CFR 50.92, this means that operation of the facility in accordance with the proposed amendment would not (1) involve a significant increase in PO 00000 Frm 00066 Fmt 4703 Sfmt 4703 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 change involve a significant increase in the probability or consequences of an accident previously evaluated? Response: No. This proposed change revises the Technical Specification (TS) Surveillance Requirement (SR) 3.3.7.a allowable values of the Degraded Voltage Function. This proposed change will allow Southern California Edison (SCE) to re-establish 218 kV as the minimum voltage on the offsite transmission grid necessary to support operability of the immediate access offsite power source (also referred to as the normal preferred power source[)]. This will be accomplished by lowering the dropout and pickup settings, including allowable values for dropout and pickup of the degraded voltage protection relays. Following approval of this proposed change, the 4.16 kV Class 1E buses would be capable of remaining on the normal preferred power source at or above a grid voltage of 218 kV while protecting all Class 1E equipment from degraded grid conditions. The degraded voltage protection circuits are designed to protect electrical equipment against the effects of degraded voltage on the offsite transmission networks. Therefore, these circuits are generally not considered to be accident initiators. However, spurious actuation of the degraded voltage protection relays could result in the loss of the preferred power source (offsite source of alternating current (AC) power). The proposed change lowers the allowable values for both dropout and pickup for the degraded voltage protection relays. This results in an increase in operating margin and a lower probability of spurious actuation of these degraded voltage signals. Therefore, there is no increase in the probability of a Loss of Offsite Power (preferred power source) as a result of this proposed change. The safety function of the degraded voltage protection circuits is to ensure the operability of Class 1E equipment. SCE has performed calculations that demonstrate that operation in accordance with this proposed change will not result in operation of plant equipment at degraded voltages. E:\FR\FM\14JNN1.SGM 14JNN1 Federal Register / Vol. 70, No. 113 / Tuesday, June 14, 2005 / Notices Therefore, there is no increase in the consequences of any accident previously evaluated. Therefore, the proposed change does not involve a significant increase in the probability or consequences of any accident previously evaluated. 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated? Response: No. The proposed allowable values of the degraded voltage relays will provide an acceptable level of protection for plant equipment. This proposed change affects only the voltage settings of the degraded voltage protection relays. There is no other change to the degraded voltage function. There are no physical modifications necessary to the degraded voltage protection relays. There are no changes to the actions performed by the relays following actuation. Therefore, there are no new failure modes or effects introduced by this proposed change. Therefore, this proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated. 3. Does the proposed change involve a significant reduction in a margin of safety? Response: No. The proposed degraded voltage protection schemes are designed to ensure that plant equipment will not operate at a degraded voltage. The proposed degraded voltage allowable values will not affect the existing protection criterion for plant equipment. This maintains the existing margin of safety for plant equipment. Therefore, there is no significant reduction in the margin of safety as a result of the proposed amendment. 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 14 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 the 14-day notice period. However, should circumstances change during the notice period, such that failure to act in a timely way would result, for example, in derating or VerDate jul<14>2003 20:14 Jun 13, 2005 Jkt 205001 shutdown of the facility, the Commission may issue the license amendment before the expiration of the 14-day notice period, provided that its final determination is that the amendment involves no significant hazards consideration. The final determination will consider all public and State comments received. Should the Commission take this action, it will publish in the Federal Register a notice of 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, Rules and Directives 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, 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 and Issuance of Orders’’ 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 01F21, 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 PO 00000 Frm 00067 Fmt 4703 Sfmt 4703 34507 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/requestor is aware and on which the petitioner/requestor intends to rely to establish those facts or expert opinion. The petitioner/requestor must provide 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/ requestor 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. E:\FR\FM\14JNN1.SGM 14JNN1 34508 Federal Register / Vol. 70, No. 113 / Tuesday, June 14, 2005 / Notices 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 email to OGCMailCenter@nrc.gov. A copy of the request for hearing and petition for leave to intervene should also be sent to Nicolas S. Reynolds, Esquire, Winston and Strawn, 1400 L Street, NW., Washington, DC 2005–3502, attorney for the licensee. For further details with respect to this action, see the application for amendment dated May 27, 2005, which VerDate jul<14>2003 20:14 Jun 13, 2005 Jkt 205001 is available for public inspection at the Commission’s 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 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, 301– 415–4737, or by e-mail to pdr@nrc.gov. Dated at Rockville, Maryland, this 7th day of June 2005. For the Nuclear Regulatory Commission. Mel B. Fields, Senior Project Manager, Section 2, Project Directorate IV, Division of Licensing Project Management, Office of Nuclear Reactor Regulation. [FR Doc. E5–3065 Filed 6–13–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Advisory Committee on the Medical Uses of Isotopes: Meeting Notice Nuclear Regulatory Commission. ACTION: Notice of meeting. AGENCY: SUMMARY: The U.S. Nuclear Regulatory Commission will convene a teleconference meeting of the Advisory Committee on the Medical Uses of Isotopes (ACMUI) on June 28, 2005. The topic of discussion will be ‘‘Update to Medical Event Criteria Definition.’’ During this discussion, an ACMUI subcommittee will forward to the full ACMUI its recommendation(s) regarding revision of the medical event criteria definition in 10 CFR part 35, ‘‘Medical Use of Byproduct Material,’’ as this definition applies to medical events involving permanent implant brachytherapy. NRC staff is seeking the ACMUI’s recommendations on this issue, as well as any recommendations on communicating associated risks to the public. DATES: The teleconference meeting will be held on Tuesday, June 28, 2005, from 1 p.m. to 3 p.m, eastern daylight time. Public Participation: Any member of the public who wishes to participate in the teleconference discussion may contact Angela R. McIntosh using the contact information below. FOR FURTHER INFORMATION CONTACT: Angela R. McIntosh, telephone (301) 415–5030; e-mail arm@nrc.gov of the PO 00000 Frm 00068 Fmt 4703 Sfmt 4703 Office of Nuclear Material Safety and Safeguards, U.S. Nuclear Regulatory Commission, Washington, DC 20555– 0001. Conduct of the Meeting Leon S. Malmud, M.D., will chair the meeting. Dr. Malmud will conduct the meeting in a manner that will facilitate the orderly conduct of business. The following procedures apply to public participation in the meeting: 1. Persons who wish to provide a written statement should submit a reproducible copy to Angela McIntosh, U.S. Nuclear Regulatory Commission, Two White Flint North, Mail Stop T8F5, Washington, DC 20555–0001. Hard copy submittals must be postmarked by June 20. Electronic submittals must be submitted by June 24, 2005. Any submittal must pertain to the topic on the agenda for the meeting. 2. Questions from members of the public will be permitted during the meeting, at the discretion of the Chairman. 3. The transcript and written comments will be available for inspection on NRC’s web site (http:// www.nrc.gov) and at the NRC Public Document Room, 11555 Rockville Pike, Rockville, MD 20852–2738, telephone (800) 397–4209, on or about March 18, 2005. Minutes of the meeting will be available on or about July 12, 2005. This meeting will be held in accordance with the Atomic Energy Act of 1954, as amended (primarily Section 161a); the Federal Advisory Committee Act (5 U.S.C. App); and the Commission’s regulations in Title 10, U.S. Code of Federal Regulations, part 7. Dated: June 8, 2005. Andrew L. Bates, Advisory Committee Management Officer. [FR Doc. E5–3062 Filed 6–13–05; 8:45 am] BILLING CODE 7590–01–P NUCLEAR REGULATORY COMMISSION Sunshine Act Meeting Agency Holding the Meetings: Nuclear Regulatory Commission. DATE: Weeks of June 13, 20, 27, July 4, 11, 18, 2005. PLACE: Commissioners’ Conference Room, 11555 Rockville Pike, Rockville, Maryland. STATUS: Public and Closed. MATTERS TOO BE CONSIDERED: AGENCY: Week of June 13, 2005 There are no meetings scheduled for the Week of June 13, 2005. E:\FR\FM\14JNN1.SGM 14JNN1

Agencies

[Federal Register Volume 70, Number 113 (Tuesday, June 14, 2005)]
[Notices]
[Pages 34506-34508]
From the Federal Register Online via the Government Printing Office [www.gpo.gov]
[FR Doc No: E5-3065]


-----------------------------------------------------------------------

NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-361 and 50-362]


Southern California Edison 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 Nos. 
NPF-10 and NPF-15, issued to Southern California Edison Company (SCE or 
the licensee), for operation of the San Onofre Nuclear Generating 
Station (SONGS), Units 2 and 3 located in San Diego County, California.
    The proposed amendment would lower the allowable values for dropout 
and pickup of the degraded voltage function. The amendment request was 
submitted on May 27, 2005, on an exigent basis because the need for a 
license amendment to change the degraded voltage function was not 
recognized by the licensee or the NRC staff until recently, and the 
licensee requests approval of the proposed amendment by July 1, 2005, 
to allow implementation of the amendment before the expected high 
summer load period.
    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.
    Pursuant to 10 CFR 50.91(a)(6) for amendments to be granted under 
exigent circumstances, the NRC staff must determine that the amendment 
request involves no significant hazards consideration.
    Under the Commission's regulations in 10 CFR 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 change involve a significant increase in the 
probability or consequences of an accident previously evaluated?
    Response: No.
    This proposed change revises the Technical Specification (TS) 
Surveillance Requirement (SR) 3.3.7.a allowable values of the Degraded 
Voltage Function. This proposed change will allow Southern California 
Edison (SCE) to re-establish 218 kV as the minimum voltage on the 
offsite transmission grid necessary to support operability of the 
immediate access offsite power source (also referred to as the normal 
preferred power source[)]. This will be accomplished by lowering the 
dropout and pickup settings, including allowable values for dropout and 
pickup of the degraded voltage protection relays. Following approval of 
this proposed change, the 4.16 kV Class 1E buses would be capable of 
remaining on the normal preferred power source at or above a grid 
voltage of 218 kV while protecting all Class 1E equipment from degraded 
grid conditions.
    The degraded voltage protection circuits are designed to protect 
electrical equipment against the effects of degraded voltage on the 
offsite transmission networks. Therefore, these circuits are generally 
not considered to be accident initiators. However, spurious actuation 
of the degraded voltage protection relays could result in the loss of 
the preferred power source (offsite source of alternating current (AC) 
power). The proposed change lowers the allowable values for both 
dropout and pickup for the degraded voltage protection relays. This 
results in an increase in operating margin and a lower probability of 
spurious actuation of these degraded voltage signals. Therefore, there 
is no increase in the probability of a Loss of Offsite Power (preferred 
power source) as a result of this proposed change.
    The safety function of the degraded voltage protection circuits is 
to ensure the operability of Class 1E equipment. SCE has performed 
calculations that demonstrate that operation in accordance with this 
proposed change will not result in operation of plant equipment at 
degraded voltages.

[[Page 34507]]

Therefore, there is no increase in the consequences of any accident 
previously evaluated.
    Therefore, the proposed change does not involve a significant 
increase in the probability or consequences of any accident previously 
evaluated.
    2. Does the proposed change create the possibility of a new or 
different kind of accident from any accident previously evaluated?
    Response: No.
    The proposed allowable values of the degraded voltage relays will 
provide an acceptable level of protection for plant equipment.
    This proposed change affects only the voltage settings of the 
degraded voltage protection relays. There is no other change to the 
degraded voltage function. There are no physical modifications 
necessary to the degraded voltage protection relays. There are no 
changes to the actions performed by the relays following actuation. 
Therefore, there are no new failure modes or effects introduced by this 
proposed change.
    Therefore, this proposed change does not create the possibility of 
a new or different kind of accident from any accident previously 
evaluated.
    3. Does the proposed change involve a significant reduction in a 
margin of safety?
    Response: No.
    The proposed degraded voltage protection schemes are designed to 
ensure that plant equipment will not operate at a degraded voltage. The 
proposed degraded voltage allowable values will not affect the existing 
protection criterion for plant equipment. This maintains the existing 
margin of safety for plant equipment.
    Therefore, there is no significant reduction in the margin of 
safety as a result of the proposed amendment.
    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 14 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 the 14-day notice period. However, should circumstances 
change during the notice period, such that failure to act in a timely 
way would result, for example, in derating or shutdown of the facility, 
the Commission may issue the license amendment before the expiration of 
the 14-day notice period, provided that its final determination is that 
the amendment involves no significant hazards consideration. The final 
determination will consider all public and State comments received. 
Should the Commission take this action, it will publish in the Federal 
Register a notice of 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, Rules and 
Directives 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, 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 and Issuance of Orders'' 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 01F21, 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/requestor is aware and on 
which the petitioner/requestor intends to rely to establish those facts 
or expert opinion. The petitioner/requestor must provide 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/
requestor 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.

[[Page 34508]]

    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 Nicolas S. Reynolds, 
Esquire, Winston and Strawn, 1400 L Street, NW., Washington, DC 2005-
3502, attorney for the licensee.
    For further details with respect to this action, see the 
application for amendment dated May 27, 2005, which is available for 
public inspection at the Commission's 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 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, 301-415-4737, or by e-
mail to pdr@nrc.gov.

    Dated at Rockville, Maryland, this 7th day of June 2005.

    For the Nuclear Regulatory Commission.
Mel B. Fields,
Senior Project Manager, Section 2, Project Directorate IV, Division of 
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. E5-3065 Filed 6-13-05; 8:45 am]
BILLING CODE 7590-01-P