[Federal Register Volume 65, Number 207 (Wednesday, October 25, 2000)]
[Notices]
[Pages 63896-63898]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 00-27381]


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NUCLEAR REGULATORY COMMISSION

[Docket No. 50-269, 50-270, and 60-287]


Duke Energy 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 (the Commission) is 
considering issuance of an amendment to Facility Operating License Nos. 
DPR-38, DPR-47, and DPR-55 issued to the Duke Energy Corporation (the 
licensee) for operation of the Oconee Nuclear Station, Units 1, 2, and 
3 located in Seneca, South Carolina.
    By letter dated June 6, 2000, the Commission approved Amendment 
Nos. 312, 312, and 312 to add Technical Specification (TS) Surveillance 
Requirement 3.8.1.17 to verify operability of the Keowee Hydro Units 
(KHUs) out-of-tolerance logic trip and closure blockage relays 
associated with the overhead and underground power path breakers. The 
amendments specified that the TS change would be implemented by 
November 30, 2000.
    Subsequently, by application dated October 18, 2000, the licensee 
submitted a proposed amendment to change the implementation date. The 
proposed new date would be based on an engineering study that is being 
conducted to evaluate the appropriate KHU OOT surveillance criteria and 
resolve overshoot concerns. These overshoot concerns are described in 
Amendment Nos. 316, 316 and 316 that were issued on October 4, 2000, 
which also added a note that requires an amendment, based on the 
results of this evaluation, be submitted by April 5, 2001.
    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 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

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analysis of the issue of no significant hazards consideration, which is 
presented below:

    Pursuant to 10 CFR 50.91, Duke Power Company (Duke) has made the 
determination that this amendment request involves a No Significant 
Hazards Consideration by applying the standards established by the 
NRC regulations in 10 CFR 50.92. This ensures 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.
    No. The License Amendment Request (LAR) involves revising the 
implementation date of November 30, 2000 for the Keowee Hydro Unit 
[KHU] out-of-tolerance [OOT] voltage and frequency modification. 
Revising this date will allow Duke to integrate resolution of the 
overshoot issues.
    This LAR involves an administrative issue, rather than the 
inability of the KHU to perform its intended safety function. The 
out-of-tolerance voltage and frequency modification is considered an 
enhancement to the existing design. Changing the implementation date 
for the modification has no impact on existing plant equipment.
    Revising the requirements for implementation does not involve: 
(1) A physical alteration to the Oconee Units; (2) operating any 
installed equipment in a new or different manner; or (3) a change to 
any set points for parameters which initiate protective or 
mitigative action.
    There is no adverse impact on containment integrity, 
radiological release pathways, fuel design, filtration systems, main 
steam relief valve set points, or radwaste systems. No new 
radiological release pathways are created.
    Therefore, the probability or consequence of an accident 
previously evaluated is not significantly increased.
    2. Create the possibility of a new or different kind of accident 
from any accident previously evaluated.
    No. The LAR involves revising the implementation date for the 
KHU voltage and frequency OOT modification.
    Delaying implementation does not involve a physical effect on 
the unit, nor is there any increased risk of a unit trip or 
reactivity excursion. No new failure modes or credible accident 
scenarios are postulated from this activity.
    Therefore, the possibility of a new or different kind of 
accident from any kind of accident previously evaluated is not 
created.
    3. Involve a significant reduction in a margin of safety.
    No. The LAR involves delaying implementation of the KHU voltage 
and frequency OOT modification. Delaying implementation will allow 
Duke to fully integrate the resolution of the overshoot issues.
    Delaying implementation does not involve: (1) A physical 
alteration of the Oconee Units; (2) the installation of new or 
different equipment; (3) operating any installed equipment in a new 
or different manner; (4) a change to any set points for parameters 
which initiate protective or mitigative action; or (5) any impact on 
the fission product barriers or safety limits.
    Therefore, this request does not involve a significant 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 
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 the 30-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 30-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 and provide for opportunity for a hearing 
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, 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.
    By November 24, 2000, 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 2.714 which is 
available at the Commission's Public Document Room, located at One 
White Flint North, 11555 Rockville Pike (first floor), Rockville, 
Maryland, and accessible electronically through the ADAMS Public 
Electronic Reading Room link at the NRC Web site (http://www.nrc.gov). 
If a request for a hearing or petition for leave to intervene is filed 
by the above date, the Commission or an Atomic Safety and Licensing 
Board, designated by the Commission or by the Chairman of the Atomic 
Safety and Licensing Board Panel, will rule on the request and/or 
petition; and the Secretary or the designated Atomic Safety and 
Licensing Board will issue a notice of hearing or an appropriate order.
    As required by 10 CFR 2.714, 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 factors: (1) The nature of the petitioner's right under the 
Act to be made party to the proceeding; (2) the nature and extent of 
the petitioner's property, financial, or other interest in the 
proceeding; and (3) the possible effect of any order which may be 
entered in the proceeding on the petitioner's interest. The petition 
should also identify the specific aspect(s) of the subject matter of 
the proceeding as to which petitioner wishes to intervene. Any person 
who has filed a petition for leave to intervene or who has been 
admitted as a party may amend the petition without requesting leave of 
the Board up to 15 days prior to the first prehearing conference 
scheduled in the proceeding, but such an amended petition must satisfy 
the specificity requirements described above.
    Not later than 15 days prior to the first prehearing conference 
scheduled in the proceeding, a petitioner shall file a supplement to 
the petition to intervene which must include a list of the contentions 
which are sought to be litigated in the matter. Each contention must 
consist of a specific statement of the issue of law or fact to be 
raised or

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controverted. In addition, the petitioner shall provide a brief 
explanation of the bases of 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. 
Petitioner 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 to relief. A petitioner who fails 
to file such a supplement which satisfies 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, including the opportunity to present evidence and cross-
examine witnesses.
    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.
    A request for a hearing or a petition for leave to intervene must 
be filed with the Secretary of the Commission, U.S. Nuclear Regulatory 
Commission, Washington, DC 20555-0001, Attention: Rulemakings and 
Adjudications Staff, or may be delivered to the Commission's Public 
Document Room, located at One White Flint North, 11555 Rockville Pike 
(first floor), Rockville, Maryland, by the above date. A copy of the 
petition should also be sent to the Office of the General Counsel, U.S. 
Nuclear Regulatory Commission, Washington, DC 20555-0001, and to Anne 
W. Cottington, Winston and Strawn, 1200 17th Street, NW., Washington, 
DC 20555, attorney for the licensee.
    Nontimely filings of petitions for leave to intervene, amended 
petitions, supplemental petitions and/or requests for hearing will not 
be entertained absent a determination by the Commission, the presiding 
officer or the presiding Atomic Safety and Licensing Board that the 
petition and/or request should be granted based upon a balancing of the 
factors specified in 10 CFR 2.714(a)(1)(i)-(v) and 2.714(d).
    For further details with respect to this action, see the 
application for amendment dated October 18, 2000, which is available 
for public inspection at the Commission's Public Document Room, located 
at One White Flint North, 11555 Rockville Pike (first floor), 
Rockville, Maryland, and accessible electronically through the ADAMS 
Public Electronic Reading Room link at the NRC Web site (http://www.nrc.gov).

    Dated at Rockville, Maryland, this 19th day of October 2000.

    For the Nuclear Regulatory Commission.
David E. LaBarge,
Senior Project Manager, Section 1, Project Directorate II, Division of 
Licensing Project Management, Office of Nuclear Reactor Regulation.
[FR Doc. 00-27381 Filed 10-24-00; 8:45 am]
BILLING CODE 7590-01-P