[Federal Register Volume 60, Number 48 (Monday, March 13, 1995)]
[Notices]
[Pages 13481-13483]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-6068]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-498]
Houston Lighting and Power Co., City Public Service Board of San
Antonio, Central Power and Light Co., City of Austin, TX; 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.
NPF-6, issued to Houston Lighting & Power Company, et al., (the
licensee) for operation of the South Texas Project (STP), Unit 1,
located in Matagorda County, Texas.
The proposed amendment would change Technical Specification 3/
4.4.5, Steam Generators, and the associated Bases to allow the use of
an alternate plugging criteria (known in the industry as F*) on steam
generator tubes that are defective or degraded within certain areas
within the tubesheet.
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 analysis of
the issue of no significant hazards consideration, which is presented
below:
1. The proposed change does not involve a significant increase
in the probability or consequences of an accident previously
evaluated.
The proposed changes to the Steam Generator section of Technical
Specifications do not affect any accident initiators or precursors
and do not alter the design assumptions for the systems or
components used to mitigate the consequences of an accident. The
requirements approved by the NRC will not be reduced by this
request. Since F* utilizes the ``as rolled'' tube configuration that
exists as part of the original steam generator design, all of the
design and operating characteristics of the steam generator and
connected systems are preserved. The F* joint has been analyzed and
tested for design, operating and faulted condition loadings in
accordance with Regulatory Guide 1.121 safety factors. At worst
case, a tube leak would occur with the result being a primary to
secondary leak.
Should a tube leak occur, the impact is bounded by the ruptured
tube evaluation submitted by HL&P [Houston Lighting & Power] for the
STP Unit 1 operating license. No new or unreviewed accident
conditions are created by the use of F* criteria. The potential for
a tube rupture is not increased from the original submittal, thus
there is no impact on accidents evaluated as the design
[[Page 13482]] basis. Therefore use of the F* criteria will not
increase the probability of occurrence of an accident previously
evaluated.
2. The proposed change does not create the possibility of a new
or different kind of accident from any accident previously
evaluated.
The use of the proposed F* alternate plugging criteria will not
introduce significant or adverse changes to the plant design basis.
The failure of a tube which remained unplugged in accordance with
the F* criteria would result in a tube leak, which is a previously
analyzed condition. Since this leak would occur below the secondary
face of the tubesheet, its leak rate would be limited by the tube-
to-tubesheet interface. Qualification testing and previous
experience indicates that normal and faulted leakage would be well
below the technical specification limits creating no threat
associated with tube rupture type leakages. This conclusion is
consistent with previous F* programs approved and used at other
operating plants.
However, in the unlikely event the failed tube severed
completely at a point below the F* region, the remaining F* joint
would retain engagement in the tubesheet due to its length of
expanded contact within the tubesheet bore, preventing any
interaction with neighboring tubes. If the tube severs at a point
above the F* region, then it is covered by the tube rupture event as
a part of the UFSAR [updated final safety analysis report]. Thus,
the possibility of a new or different type of accident from any
accident previously evaluated is not credited.
3. The proposed change does not involve a significant reduction
in a margin of safety.
Based on previous responses (above), the protective boundaries
of the steam generator are preserved. A tube with degradation can be
kept in service through F* criteria which provided an un-degraded
expanded interface with the tubesheet and which satisfies all of the
necessary structural and leakage requirements per Reg. Guide 1.121
and the Technical Specifications. Since the joint is constrained
within the tubesheet bore there is no additional risk associated
with tube rupture. Since the UFSAR analyzed accident scenarios
remain bounding the use of an F* criteria does not reduce the margin
of safety.
Thus, these changes do not involve a significant reduction in
the margin of safety. Therefore, based on the above evaluation,
Houston Lighting & Power has concluded that these changes do not
involve any significant hazards considerations.
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 Rules Review and
Directives Branch, Division of Freedom of Information and Publications
Services, Office of Administration, U.S. Nuclear Regulatory Commission,
Washington, DC 20555, and should cite the publication date and page
number of this Federal Register notice. Written comments may also be
delivered to Room 6D22, 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 April 12, 1995, 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 Wharton County Junior College, J.M. Hodges
Learning Center, 911 Boling Highway, Wharton, Texas 77488. 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 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 [[Page 13483]] 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, Attention: Docketing and Services
Branch, or may be delivered to the Commission's Public Document Room,
the Gelman Building, 2120 L Street, NW., Washington, DC, by the above
date. Where petitions are filed during the last 10 days of the notice
period, it is requested that the petitioner promptly so inform the
Commission by a toll-free telephone call to Western Union at 1-(800)
248-5100 (in Missouri 1-(800) 342-6700). The Western Union operator
should be given Datagram Identification Number N1023 and the following
message addressed to William D. Beckner, Director, Project Directorate
IV-1: petitioner's name and telephone number, date petition was mailed,
plant name, and publication date and page number of this Federal
Register notice. A copy of the petition should also be sent to the
Office of the General Counsel, U.S. Nuclear Regulatory Commission,
Washington, DC 20555, and to Jack R. Newman, Esq., Newman & Holtzinger,
P.C., 1615 L Street, NW., Washington, DC 20036, 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 March 1, 1995, 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 Wharton County Junior College, J.M. Hodges
Learning Center, 911 Boling Highway, Wharton, Texas 77488.
Dated at Rockville, Maryland, this 7th day of March 1995.
For the Nuclear Regulatory Commission.
Thomas W. Alexion,
Project Manager, Project Directorate IV-1, Division of Reactor Projects
III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 95-6068 Filed 3-10-95; 8:45 am]
BILLING CODE 7590-01-M
