[Federal Register Volume 63, Number 125 (Tuesday, June 30, 1998)]
[Notices]
[Pages 35615-35617]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-17354]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-302]
Crystal River Unit 3; 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 No.
DPR-72 issued to Florida Power Corporation (the licensee), for
operation of Crystal River Unit 3, located in Citrus County, Florida.
The proposed amendment would allow operation with a number of
indications previously identified as tube end anomalies (TEA) and
multiple tube end anomalies (MEA) in the Crystal River Unit 3 (CR-3)
Once Through Steam Generator (OTSG) tubes. The duration of the proposed
license amendment would be until CR-3's next refueling outage,
currently scheduled for fall 1999. This proposed change may be
necessary due to the potential condition of noncompliance with CR-3
Improved Technical Specification 5.6.2.10.4.b. Such a condition may
result from confirmation of an ongoing re-analysis of eddy current
testing (ECT) data, of indications previously identified as TEAs and
MEAs in the upper roll expansion of the OTSG upper tube sheet, as now
being within the pressure boundary of the tubes.
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:
This change does not involve a significant hazards consideration
for the following reasons:
(1) Involve a significant increase in the probability or
consequences of an accident previously evaluated.
This evaluation addresses the potential effects of operating
with TEAs and MEAs within the pressure boundary cladding region. The
indications remaining in service are within the upper end of the
tube pressure boundary. Two accidents analyzed in the SAR [safety
analysis report] must be evaluated: Steam Generator Tube Rupture and
Main Steam Line Break.
The steam generator tube rupture accident assumptions bound the
possible effects of leaving these indications in service. A complete
circumferential severance of a tube is assumed in the accident
scenario. The location of these indications in the upper tubesheet
precludes a tube rupture from occurring (the tubes are restrained by
the tubesheet). Additionally, in the event of a complete
circumferential severance, the tube will not retract from the
tubesheet. Thus, the probability of occurrence of this accident is
not increased by leaving these indications in service.
The main steam line break accident is not initiated by the
condition of the tubing. However, an assumption of one gpm primary-
to-secondary leakage through the OTSG is assumed in the MSLB [main
steam line break] accident analysis. Calculated cumulative leakage,
assuming all of the indications are leaking, is determined to be
well below one gpm, thus the accident analysis initial assumptions
bound the existing condition of the OTSGs. Thus, it is concluded
that the probability of occurrence of a main steam line break is not
increased by this change. Therefore, this change does not involve a
significant increase in the probability or consequences of an
accident previously evaluated.
(2) Create the possibility of a new or different kind of
accident from any accident previously evaluated.
No new failure modes or accident scenarios are created by
allowing operation with TEAs and MEAs extending within the tubes'
pressure boundary. The TEAs and MEAs remaining in service are within
the upper end of the tube pressure boundary and even in the event of
a complete circumferential severance, the tube will not retract from
the tubesheet. Therefore, the tubesheet hoop effect will still act
to minimize leakage. The postulated potential leakage generated from
allowing these indications to remain in service is bounded by the
CR-3 MSLB scenario. The MSLB scenario has been thoroughly evaluated
and the potential damage to the steam generator tubes is not
increased. This change does not increase the risk of a plant trip or
challenge other safety systems. Therefore, this change does not
create a possibility of a new or different kind of accident from any
previously evaluated.
(3) Involve a significant reduction in a margin of safety.
ITS Bases 3.4.12 contains relevant information pertaining to the
limitations on RCS [reactor coolant system] leakage. These Bases
discuss the one gpm primary-to-secondary leakage assumed for a main
steam line break accident as well as the steam generator tube
rupture accident. As discussed, the maximum calculated accident
leakage, assuming all of these indications leak, is well below one
gpm. Therefore, the margin of safety as defined in the ITS bases is
not significantly reduced.
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
[[Page 35616]]
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. Copies of
written comments received may be examined at the NRC Public Document
Room, the Gelman Building, 2120 L Street, NW., Washington, DC.
The filing of requests for hearing and petitions for leave to
intervene is discussed below.
By July 30, 1998 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, the Gelman
Building, 2120 L Street, NW., Washington, DC and at the local public
document room located at the Coastal Region Library, 8619 W. Crystal
Street, Crystal River, Florida 34428. 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 a 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 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 the amendment is issued before the expiration of the 30-day
hearing period, the Commission will make a final determination on the
issue of no significant hazards consideration. If a hearing is
requested, 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, the Gelman Building, 2120 L Street, NW., Washington, DC,
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 R. Alexander Glenn, General Counsel,
Florida Power Corporation, MAC--A5A, P. O. Box 14042, St. Petersburg,
Florida 33733-4042, 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
[[Page 35617]]
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 June 18, 1998, which is available for
public inspection at the Commission's Public Document Room, the Gelman
Building, 2120 L Street, NW., Washington, DC, and at the local public
document room, located at the Coastal Region Library, 8619 W. Crystal
Street, Crystal River, Florida.
Dated at Rockville, Maryland, this 23rd day of June 1998.
For the Nuclear Regulatory Commission.
Leonard A. Wiens,
Senior Project Manager, Project Directorate II-3, Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 98-17354 Filed 6-29-98; 8:45 am]
BILLING CODE 7590-01-P
