[Federal Register Volume 70, Number 165 (Friday, August 26, 2005)]
[Notices]
[Pages 50424-50426]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: E5-4684]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-302]
Florida Power Corporation; 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 (NRC, the Commission) is
considering issuance of an amendment to Facility Operating License No.
290, issued to Florida Power Corporation (the licensee, also doing
business as Progress Energy-Florida,) for operation of the Crystal
River Unit 3 (CR-3) Nuclear Generating Plant located in Citrus County,
FL.
The proposed amendment would allow the licensee to utilize a
probabilistic methodology to determine the contribution to main
steamline break (MSLB) leakage rates for the once-through steam
generator (OTSG) from the tube end crack (TEC) alternate repair
criteria (ARC) described in CR-3 Improved Technical Specification (ITS)
5.6.2.10.2.f. This amendment revision involves a change to ITS
5.6.2.10.2.f to incorporate the basis of the proposed probabilistic
methodology and the method and technical justification for projecting
the TEC leakage that may develop during the next operating cycle
following each inservice inspection of the CR-3 OTSGs. This notice
supercedes the previous notice dated March 15, 2005 (70 FR 12746).
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 not involve a significant increase in the probability or
consequences of an accident previously evaluated.
This LAR [license amendment request] proposes to change the
method to determine the projected MSLB leakage rates for TEC.
Potential leakage from OTSG tubes, including leakage contribution
from TEC, is bounded by the MSLB evaluation presented in the CR-3
Final Safety Analysis Report (FSAR) and testing performed during the
development of Topical Report BAW-2346P, Revision 0. The inspection
required by the ARC will continue to be performed as required by CR-
3 ITS 5.6.2.10. This inspection provides continuous monitoring of
tubes with TEC indications remaining in service, and ensures that
degradation of new tubes containing TEC indications is detected. The
proposed change in method to determine MSLB leakage rates for TEC
and the addition of a method to project the TEC leakage that may
develop during the next operating cycle do not change any accident
initiators.
2. Does not create the possibility of a new or different type of
accident from any accident previously evaluated.
This LAR proposes to change the method to determine the
projected MSLB leakage rates for TEC and the addition of a method to
project the TEC leakage that may develop during the next operating
cycle. The changes introduce no new failure modes or accident
scenarios. The proposed changes do not change the assumptions made
in Topical Report BAW-2346P, Revision 0, which demonstrated
structural and leakage integrity for all normal operating and
accident conditions for CR-3. The addition of a method to project
the TEC leakage provides an additional means to monitor the
initiation of TEC. The design and operational characteristics of the
OTSGs are not impacted by the use of a probabilistic methodology to
determine MSLB leakage rates.
3. Does not involve a significant reduction in the margin of
safety.
This LAR proposes to change the method to determine the
projected MSLB leakage rates for TEC and the addition of a method to
project the TEC leakage that may develop during the next operating
cycle. The resulting leakage estimates will be lower than the
estimates from the old method. However, the estimates from the
proposed method will be more realistic and do not impact the
acceptance criteria. The methodology relies on the same accident
analyses described in Topical Report BAW-2346P, Revision 0, and
License Amendment Request 249, Revision 0, and utilizes the
same leakage test data and leakage limit. The CR-3 FSAR analyzed
accident scenarios are not affected by the change and remain
bounding. The limits established in CR-3 ITS 3.4.12 and 5.6.2.10.2.f
have not been changed. The addition of a method to project the TEC
leakage that may develop during the next operating cycle provides an
additional means to monitor the initiation of TEC. Therefore, the
proposed change does not reduce the 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
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-
[[Page 50425]]
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, 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 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 public document room (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 particularly the interest of the petitioner/
requestor 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 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/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.
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(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 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:
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
[email protected]. A copy of the request for hearing and petition
for leave to intervene should also be sent to David T. Conley,
Associate General Counsel II--Legal Department, Progress Energy
Services Company, LLC, Post Office Box 1551, Raleigh, North Carolina
27602, attorney for the licensee.
For further details with respect to this action, see the
application for amendment dated August 12, 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://
[[Page 50426]]
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 22nd day of August, 2005.
For the Nuclear Regulatory Commission.
Brenda L. Mozafari,
Senior Project Manager, Section 2, Project Directorate II, Division of
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. E5-4684 Filed 8-25-05; 8:45 am]
BILLING CODE 7590-01-P