[Federal Register Volume 63, Number 88 (Thursday, May 7, 1998)]
[Notices]
[Pages 25243-25245]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 98-12179]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-390]
Tennessee Valley Authority; 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-90, issued to the Tennessee Valley Authority (TVA or the licensee)
for operation of the Watts Bar Nuclear Plant (WBN), Unit 1 located in
Rhea County, Tennessee.
WBN currently has two containment hydrogen ignitors that are
inoperable due to an apparent fault in the common circuit supplying
these ignitors. This condition renders Train A of the WBN
[[Page 25244]]
hydrogen mitigation system (HMS) inoperable in accordance with TS
limiting condition for operation (LCO) 3.6.8. The condition was
discovered during routine surveillance testing to the Train A ignitors
on April 3, 1998, at which time WBN entered Condition A of limiting
condition for operation (LCO) 3.6.8. The ignitors are located in a very
high radiation and temperature area of lower containment and cannot be
repaired until the reactor is taken offline. WBN's next scheduled
outage for refueling is in February 1999. The proposed amendment would
revise the TS LCO 3.6.8 to provide temporary requirements for hydrogen
ignitors to address the two Train A ignitors which are currently out of
service. The revision would apply until the next shutdown to MODE 3
following which time ignitor repairs would be performed to restore the
HMS to an operable status.
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:
TVA has concluded that operation of WBN in accordance with the
proposed change to the TS does not involve a significant hazards
consideration. TVA's conclusion is based on its evaluation in
accordance with 10 CFR 50.91(a)(1) of the three standards set forth
in 10 CFR 50.92(c).
(A) The proposed amendment does not involve a significant
increase in the probability or consequences of an accident
previously evaluated.
The proposed temporary technical specification would permit two
specific Train A ignitors (30A and 31A) in non-adjacent regions to
be out of service until the next WBN entry into MODE 3. In this
condition, the remaining 32 of 34 ignitors, in combination with
thorough containment air mixing and with the hydrogen collection
function of the air return system, will maintain the ability to burn
hydrogen such that containment hydrogen remains low following a
degraded core accident. Thus, the design basis of the HMS will be
maintained such that a controlled hydrogen burn may occur at the
lower flammability concentration following a degraded core accident.
In addition, although a loss of Train B power could result in loss
of ignitors in two regions of lower containment, the short duration
allowed by the proposed amendment for this condition (not to exceed
72 hours) minimizes the likelihood of a concurrent accident
requiring the ignitors. The WBN PSA [probabilistic safety
assessment] establishes a probability of 3.6 x 10-7
events per reactor-year of a degraded core event based on 72 hours,
with the probability more remote for an accident that would generate
hydrogen in amounts equivalent to a metal-water reaction of 75% of
core cladding for which the HMS is intended. Additionally,
sufficient ignition capability in adjacent regions combined with
containment air mixing would provide capability by flame propagation
to the regions with no operable ignitors. Thus the failure of the
two specific ignitors should not result in any change to the post-
accident hydrogen burn profiles. Since the hydrogen concentration
would remain low and pocketing which could lead to rapid burns and
challenge containment is unlikely, the original design continues to
be met. Thus the probability of a containment failure and associated
radiological release is insignificantly altered. Because the
containment response will not change, the proposed TS will not
result in an increase in the probability or consequences of any
accident previously evaluated in the WBN FSAR.
(B) Operation of the facility in accordance with the proposed
amendment would not create the possibility of a new or different
kind of accident from any accident previously evaluated.
As discussed above, with the two Train A ignitors out of
service, the remaining 32 of 34 ignitors in combination with
containment air mixing will maintain the design basis of the HMS
such that a controlled hydrogen burn may be accomplished following a
degraded core accident, including a short time period of 72 hours
for which a loss of Train B power could result in loss of ignitors
in two regions of lower containment. Since the failure of the
ignitors should not result in any change to the post-accident
hydrogen burn profiles and because the containment response will not
change, the proposed TS will not result in any new or different kind
of accident from any accident previously evaluated.
(C) Operation of the facility in accordance with the proposed
amendment would not involve a significant reduction in margin of
safety.
Although the HMS is not provided for a design basis accident
(DBA), the Bases of the WBN TS define the design function of the HMS
as having the capability to burn hydrogen in a controlled manner at
the lower flammability concentration following a degraded core
accident. An ignitor train is currently considered OPERABLE with at
least 33 of 34 ignitors in service and each containment region
having at least one operable ignitor. Although the proposed TS
change would allow two specific Train A ignitors to be out of
service and their associated containment regions to be without any
ignitors for a short duration (72 hours), the remaining 32 of 34
ignitors will maintain the design basis of the HMS such that a
controlled hydrogen burn may be accomplished following a degraded
core accident. Although small increases in the hydrogen flammability
concentration may occur, deflagration would still be expected to
occur in a controlled manner and prior to a high hydrogen
concentration. As stated earlier, failure of the two ignitors should
not result in any change to the post-accident hydrogen burn profiles
or containment response. Therefore, the proposed TS change will not
involve a significant reduction in 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 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.
[[Page 25245]]
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 June 8, 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 Chattanooga-Hamilton County Library, 1001
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 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 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, 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 General Counsel, Tennessee Valley
Authority, ET 10H, 400 East 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 April 29, 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 Chattanooga-Hamilton County Library, 1001
Broad Street, Chattanooga, Tennessee.
Dated at Rockville, Maryland, this 1st day of May 1998.
For the Nuclear Regulatory Commission
Robert E. Martin,
Project Manager, Project Directorate II-3 , Division of Reactor
Projects--I/II, Office of Nuclear Reactor Regulation.
[FR Doc. 98-12179 Filed 5-6-98; 8:45 am]
BILLING CODE 7590-01-P
