[Federal Register Volume 59, Number 119 (Wednesday, June 22, 1994)]
[Unknown Section]
[Page 0]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 94-15266]
[[Page Unknown]]
[Federal Register: June 22, 1994]
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NUCLEAR REGULATORY COMMISSION
[Docket No. 50-461]
Illinois Power Co.; 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-62, issued to the Illinois Power Company (the licensee), for
operation of the Clinton Power Station, Unit 1, located in DeWitt
County, Illinois.
The proposed amendment would modify Technical Specification 3/
4.4.3.1, ``Reactor Coolant System Leakage--Leakage Detection Systems,''
to permit continued plant operation with inoperable drywell floor drain
sump flow rate monitoring instrumentation. Continued plant operation
would be permitted until the first time the plant is required to be
brought to COLD SHUTDOWN after July 10, 1994.
Technical Specification 3/4.4.3.1 requires that systems capable of
monitoring unidentified reactor coolant system leakage rates remain
operable. Rector coolant system leakage that falls on the drywell
floors is channeled through the floor drains and enters the drywell
floor drain sump. Prior to entering the floor drain sump, water passes
through the drywell floor drain sump flow monitoring instrumentation
where the instantaneous flow rates and total integrated flow are
measured. The flow monitoring instrumentation consists of a V-notch
weir box containing a capacitance probe. Water flows through a V-notch
water level which is directly proportional to the flow through the weir
box. Thus, flow through the V-notch is equal to the sump inlet flow
rate. The capacitance probe is calibrated to correspond to the incoming
flow rate and provides a continuous control room indication of the
unidentified reactor coolant system leakage rate. An alarm is generated
when the technical specification limit of 5 gpm of unidentified leakage
occurs. The V-notch weir box instrumentation meets the accuracy and
sensitivity requirements of Regulatory Guide 1.45 for drywell floor
drain sump flow monitoring.
The licensee began to observe questionable readings from the
indicated drywell floor drain sump inlet flow and subsequently declared
the drywell floor drain sump monitoring instrumentation inoperable on
June 10, 1994. Technical Specification 3.4.3.1 permits 30 days of
continuous plant operation provided the drywell floor drain sump flow
rate is monitored and determined by alternative means at least once
every 8 hours.
All efforts by the licensee to restore the drywell sump inlet flow
monitoring instrumentation to operable status have been unsuccessful.
The instrument loop has been recalibrated and equipment external to the
drywell has been verified to be operating properly. The only option
remaining for the licensee is to enter the drywell in order to examine
the V-notch weir box and associated capacitance probe. However, the V-
notch weir box is located in a keyway beneath the reactor vessel and
inside the biological shield wall. Due to the high radiation and
temperatures in this location, a plant shutdown would be required
before personnel would be able to reach the instrumentation.
In a letter dated June 20, 1994, the licensee requested that this
amendment application be treated as an emergency because unless
approved, technical specifications would require a plant shutdown. The
licensee stated that such action would be necessary to preclude an
unnecessary plant transient and related plant risk associated with a
plant shutdown. Due to time constraints, sufficient time is not
available to permit the customary public notices in advance of this
action.
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:
(1) The proposed change does not affect any initiators of any
previously evaluated accidents. Additionally, the proposed change
involves equipment that only provides indication and therefore, it
cannot increase the probability of any accident previously
evaluated.
As stated in Updated Safety Analysis Report (USAR) Section
7.7.1.24.1, no credit is taken in the safety analysis for operation
of or operator reliance upon the leakage detection monitoring
instrumentation associated with the drywell sumps. Notwithstanding,
the drywell floor drain sump flow monitoring system provides the
capability to detect and measure leakage from unknown sources of
leakage in the drywell. The drywell floor drain sump inlet flow
monitoring V-notch weir box instrumentation is designed to meet the
accuracy requirements of Regulatory Guide 1.45. This instrumentation
does not provide any automatic action or control functions. In
addition to the V-notch system, drywell floor drain sump flow rates
can be determined by using the sump pump pump-out timers, cycle
counters and level switches. In addition, unidentified leakage into
the drywell is monitored by a flow rate meter in the condensate
discharge line from the drywell air coolers and by a particulate and
a gaseous radiation monitoring channel of the drywell fission
product monitor. While the drywell fission product monitor does not
provide a quantitative leakage rate, it is sensitive enough to
provide plant operators with early indication of an unanticipated
increase in unidentified leakage. Furthermore, a number of other
parameters are monitored with appropriate instrumentation to provide
the plant operators with indirect indication of increases in
unidentified leakage. These parameters include drywell pressure and
drywell temperature. These alternative methods of detecting
increases in unidentified leakage rates provide operators with
sufficient information to take appropriate action to respond to an
increase in leakage. Based on the above, Illinois Power concludes
that the proposed change will not increase the consequences of any
accident previously evaluated.
(2) The proposed change does not involve any modification to
plant structures or components and only involves equipment that
provides indication of leakage to the plant operators. The affected
equipment does not provide any automatic action or control
functions. As a result, the proposed change does not involve a
change in the operation of the plant, nor does it introduce any new
failure modes. Therefore, this proposed change cannot create the
possibility of a new or different kind of accident from any accident
previously evaluated.
(3) The margin of safety associated with the instrumentation
affected by the proposed change may be related to the limits on
unidentified leakage. As stated in the Bases for Technical
Specification 3/4.4.3.2. ``The allowable leakage rates from the
reactor coolant system have been based on the predicted and
experimentally observed behavior of cracks in pipes . . . The
evidence obtained from experiments suggests that for leakage
somewhat greater than that specified for unidentified leakage the
probability is small that the imperfection or crack associated with
such leakage would grow rapidly. With respect to Intergranular
Stress Corrosion Cracking (IGSCC) related cracks in service
sensitive austenitic stainless steel piping however, an additional
limit on the allowed increase in unidentified leakage (within a 24-
hour period or less) is imposed in accordance with NRC Generic
Letter 88-01, `NRC Position on IGSCC in BWR Austenitic Stainless
Steel Piping,' since an abrupt increase in the unidentified leakage
could be indicative of leakage from such a source.'' The proposed
change does not alter any of these limits on the unidentified
leakage.
As previously described, flow rates into the drywell floor drain
sump can be determined based on the indicated run time for the sump
pumps and the known pump flow rates or by monitoring the sump fill-
up times and considering the volume corresponding to the current
level control band. These alternate methods are sufficient to
determine whether unidentified leakage in the drywell exceeds the 5
pgm limit and whether changes in this leakage exceed the limit of a
2 gpm increase in any 24-hour period or less.
Additionally, with respect to the ability to detect changes in
unidentified leakage rates, in addition to the V-notch system,
drywell floor drain sump flow rates can be determined by using the
sump pump pump-out timers, cycle counters and level switches. In
addition, unidentified leakage into the drywell is monitored by a
flow rate meter in the condensate discharge line from the drywell
air coolers and by a particulate and a gaseous radiation monitoring
channel of the drywell fission product monitor. While the drywell
fission product monitor does not provide a quantitative leakage
rate, it is sensitive enough to provide plant operators with early
indication of an unanticipated increase in the unidentified leakage
rate involving reactor coolant. Furthermore, a number of other
parameters are monitored with appropriate instrumentation to provide
the plant operators with indirect indication of increases in
unidentified leakage. These parameters include drywell pressure and
drywell temperature.
As stated above, the drywell floor drain sump flow monitoring
instrumentation does not provide any automatic action or control
functions. Further, as stated in USAR Section 7.7.1.24.1, no credit
is taken in the safety analysis for operation of or operator
reliance upon the leakage detection monitoring instrumentation
associated with the drywell sumps.
In light of all the above, Illinois Power concludes that the
proposed change does not involve a 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 15 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 15-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 15-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 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, 11555 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 July 22, 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 Vespasian Warner Public Library,
120 West Johnson Street, Clinton, Illinois, 61727. 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 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 providing 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 significant
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, 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 John Hannon, Director, Project
Directorate III-3; 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 Sheldon Zabel, Esq., Schiff,
Hardin and Waite, 7200 Sears Tower, 233 Wacker Drive, Chicago, Illinois
60606, 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 June 20, 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 Vespasian Warner Public Library,
120 West Johnson Street, Clinton, Illinois 61727.
For the Nuclear Regulatory Commission.
Douglas V. Pickett,
Acting Director, Project Directorate III-3, Division of Reactor
Projects-III-IV, Office of Nuclear Reactor Regulation.
[FR Doc. 94-15266 Filed 6-21-94; 8:45 am]
BILLING CODE 7590-01-M