[Federal Register Volume 59, Number 180 (Monday, September 19, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-23141]
[[Page Unknown]]
[Federal Register: September 19, 1994]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-327 and 50-328]
Sequoyah Nuclear Plant Units 1 and 2; 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 amendments to Facility Operating License Nos.
DPR-77 and DPR-79 issued to the Tennessee Valley Authority (the
licensee) for operation of the Sequoyah Nuclear Plant, Units 1 and 2,
located in Soddy Daisy, Tennessee.
The proposed amendments, submitted by the licensee's letter dated
September 8, 1994, would incorporate a clarification to separate the
portion of the steam generator tubing from the end of the tube up to
the start of the tube-to-tubesheet weld from the remainder of the tube
for the purposes of sample selection and repair when defects are found
in this section of a steam generator tube.
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 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:
TVA has evaluated the proposed technical specification (TS)
change and has determined that it does not represent a significant
hazards consideration based on criteria established in 10 CFR
50.92(c). Operation of Sequoyah Nuclear Plant (SQN) in accordance
with the proposed amendment will not:
1. Involve a significant increase in the probability or
consequences of an accident previously evaluated.
This change will clarify the requirements for indications found
in the region of the steam generator (S/G) tube, which protrudes
below the tubesheet. This region of the tube does not affect the
structural integrity of the reactor coolant system (RCS) pressure
boundary, since it is not part of the pressure boundary. This
revision will exempt this portion of the tube from being considered
under the result and action required sections of Table 4.4-2 in
SQN's TS. Therefore, indications in this region will not require
repairs and will not be used for the purpose of expanding the sample
of tubes to be inspected under the requirements of the TS.
The condition described in this evaluation results in tube
integrity considerations commensurate with Regulatory Guide 1.121
criteria both analytically and empirically. If the indications are
hypothetically considered as cracks, the Row 1 tube end indications
neither adversely affect S/G tube integrity or any other component,
nor does the presence of the indications alter the function of the
S/G or any other component. Continuing the hypothetical scenario,
even if the crack propagated beyond the weld, the only consequence
of an accident that could be caused by plant operation or by the
occurrence of a faulted condition event with the tube end
indications, would be negligible leakage from the primary to
secondary system. Such leakage is expected to be insignificant at
both normal and faulted conditions. Therefore, plant operation with
the tube end indications present in the Row 1 tubes does not
increase the probability of an analyzed accident such as a S/G tube
rupture event,
2. Create the possibility of a new or different kind of accident
from any previously analyzed.
Any hypothetical accident as a result of plant operation with
the Row 1 tube end indications would be bounded by the consequences
of a postulated S/G tube rupture. Therefore, this change does not
create the possibility of a new or different kind of accident from
any previously analyzed.
3. Involve a significant reduction in a margin of safety.
The locations of the axial indications observed are below the
tube-to-tubesheet weld. Consequently, it is concluded that the axial
indications do not affect the structural and leakage integrity of
the primary pressure boundary. Should the indications be single or
multiple axial cracks on the tube ends, the effect of crack
propagation was evaluated. Tube burst is precluded for cracks within
the tubesheet by the constraint provided by the tubesheet.
Therefore, crack lengths do not need to be limited by burst
considerations and operating leakage limits are not required to
detect crack lengths associated with the tube burst. However,
primary to secondary leakage must be shown to remain within
acceptable limits during all plant conditions. Leak-rate testing
shows that such leakage would be negligible during all plant
conditions. Since the pressure boundary integrity, acceptable leak
rate, and function of the S/G are not affected by the presence of
the tube end indications, the margin of safety is not 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 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 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 required.
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
20555.
The filing of requests for hearing and petitions for leave to
intervene is discussed below.
By October 19, 1994, 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 20555 and at the local
public document room located at the Chattanooga-Hamilton County
Library, 1101 Broad Street, Chattanooga, Tennessee 37402. 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
particularly 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 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 20555, 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 Mr. Frederick J. Hebdon: 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 General Council, Tennessee Valley Authority, ET 11H, 400 West Summit
Hill Drive, Knoxville, Tennessee 37902, 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 September 8, 1994, which is available
for public inspection at the Commission's Public Document Room, the
Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at the
local public document room located at the Chattanooga-Hamilton County
Library, 1101 Broad Street, Chattanooga, Tennessee 37402.
Dated at Rockville, Maryland, this 13th day of September 1994.
David E. LaBarge, Sr.
Project Manager, Project Directorate II-4, Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 94-23141 Filed 9-16-94; 8:45 am]
BILLING CODE 7590-01-M
