[Federal Register Volume 71, Number 82 (Friday, April 28, 2006)]
[Notices]
[Pages 25249-25251]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E6-6427]


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NUCLEAR REGULATORY COMMISSION

[Docket Nos. 50-280 and 50-281]


Virginia Electric and Power Company; Notice of Consideration of 
Issuance of Amendments to Facility Operating Licenses, Proposed No 
Significant Hazards Consideration Determination, and Opportunity for a 
Hearing

    The U.S. Nuclear Regulatory Commission (the Commission) is 
considering issuance of amendments to Facility Operating License Nos. 
DPR-32 and DPR-37 issued to Virginia Electric and Power Company (the 
licensee) for operation of the Surry Power Station, Unit Nos. 1 and 2, 
located in Surry County, Virginia.
    The proposed amendments would reinstate previous reactor coolant 
system (RCS) pressure and temperature (P/T) limits, low temperature 
overpressure protection system (LTOPS) setpoint, and LTOPS enable 
temperature basis.
    Before issuance of the proposed license amendments, 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 requested 
amendments involve 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 amendments 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 change involve a significant increase in the 
probability or consequences of an accident previously evaluated?
    The proposed change does not impact the condition or performance 
of any plant structure, system or component. The proposed change 
does not affect the initiators of any previously analyzed event or 
the assumed mitigation of accident or transient events since the 
plant will be operated in the same manner and within the same 
operating limits that are currently in place. The proposed change 
merely restores the RCS P/T limit curves and LTOPS setpoint that 
were approved by the NRC prior to the issue of License Amendments 
245/244, and which are currently in effect. As a result, the 
proposed change to the Surry TS [Technical Specifications] does not 
involve any increase in the probability or the consequences of any 
accident or malfunction of equipment important to safety previously 
evaluated since neither accident probabilities nor consequences are 
being affected by this proposed change.
    2. Does the change create the possibility of a new or different 
kind of accident from any accident previously evaluated?
    The proposed change does not involve any changes in station 
operation or physical modifications to the plant. In addition, no 
changes are being made in the methods used to respond to plant 
transients that have been previously analyzed. No changes are being 
made to plant parameters within which the plant is normally operated 
or in the setpoints, which initiate protective or mitigative 
actions, since the plant will be operated in the same manner and 
within the same operating limits that are currently in place. Since 
plant operation will not be affected by this change, no new failure 
modes are being introduced. Therefore, the proposed change to the 
Surry TS does not create the possibility of a new or different kind 
of accident or malfunction of equipment important to safety from any 
previously evaluated.
    3. Does the change involve a significant reduction in the margin 
of safety?
    The return to the previously approved RCS P/T operating limit 
curves and LTOPS

[[Page 25250]]

setpoint does not involve a significant reduction in the margin of 
safety. The proposed change does not impact station operation or any 
plant structure, system or component that is relied upon for 
accident mitigation. Furthermore, the margin of safety assumed in 
the plant safety analysis is not affected in any way by the proposed 
change since the plant will be operated in the same manner and 
within the same operating limits and setpoints that are currently in 
place. Therefore, the proposed change to the Surry [TSs] does not 
involve any reduction in a margin of safety.

    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 
requested amendments involve 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 amendments until the 
expiration of 60 days after the date of publication of this notice. The 
Commission may issue the license amendments before expiration of the 
60-day period provided that its final determination is that the 
amendments involve no significant hazards consideration. In addition, 
the Commission may issue the amendments 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, 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, Public File Area O1 F21, 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 amendments 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 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/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 requested amendments involve no 
significant hazards consideration, the Commission may issue the 
amendments and make it immediately effective, notwithstanding the 
request for a hearing. Any hearing held would take place after issuance 
of the amendments. If the final determination is that the requested 
amendments involve a significant hazards consideration, any hearing 
held would take place before the issuance of these amendments.
    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).

[[Page 25251]]

    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, [email protected]; 
or (4) facsimile transmission addressed to the Office of the Secretary, 
U.S. Nuclear Regulatory Commission, Washington, DC, Attention: 
Rulemaking 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 
[email protected]. A copy of the request for hearing and petition 
for leave to intervene should also be sent to Ms. Lillian M. Cuoco, 
Dominion Resources Services, Inc., Building 475, 5th Floor, Rope Ferry 
Road, Waterford, Connecticut 06385, attorney for the licensee.
    For further details with respect to this action, see the 
application for amendments dated April 20, 2006, 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 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 [email protected].

    Dated at Rockville, Maryland, this 21st day of April 2006.
    For the Nuclear Regulatory Commission.
Stephen Monarque,
Project Manager, Plant Licensing Branch II-1, Division of Operating 
Reactor Licensing, Office of Nuclear Reactor Regulation.
 [FR Doc. E6-6427 Filed 4-27-06; 8:45 am]
BILLING CODE 7590-01-P