[Federal Register Volume 61, Number 39 (Tuesday, February 27, 1996)]
[Notices]
[Pages 7281-7283]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-4343]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-373 AND 50-374]
Commonwealth Edison Co.; Notice of Consideration of Issuance of
Amendments to Facility Operating Licenses, Proposed No Significant
Hazards Consideration Determination, and Opportunity for a Hearing
The U.S. Nuclear Regulatory Commission (the Commission) is
[[Page 7282]]
considering issuance of amendments to Facility Operating License Nos.
NPF-11 and NPF-18 issued to Commonwealth Edison Company (ComEd, the
licensee) for operation of the LaSalle County Station, Units 1 and 2,
located in LaSalle County, Illinois.
The proposed amendment would change the setpoints for the automatic
primary containment isolation signal upon detection of a high main
steamline tunnel differential temperature. Additionally, the proposed
amendments would delete the automatic isolation function upon detection
of a high main steamline tunnel temperature. Both these temperature
generated signals detect possible steam leaks in the main steamline
tunnel and initiate the isolation signals cited above, thereby
providing automatic closure of the main steamline isolation valves
(MSIVs) and the main steamline drain isolation valves. The intent of
the proposed actions is to minimize spurious isolation signals which,
in turn, would trip the reactor. The licensee proposes to provide for
early detection of a main steamline break by relying on an automatic
isolation signal which would be generated by a main steamline leak of
100 gallons per minute (gpm) or greater. The current isolation
setpoints are based on a steam leakage of 25 gpm in the main steamline
tunnel.
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) Involve a significant increase in the probability or
consequences of an accident previously evaluated because:
a. There is no effect on accident initiators so there is no
change in probability of an accident. The accident analysis
associated with a steam line break in the main steam line tunnel
assumes an instantaneous circumferential break of a main steam line
downstream of the outermost isolation valve. The leak detection
isolation on differential temperature based on less than or equal to
10 percent of a calculated critical crack of a main steam line is
only a precursor of a break, and thus does not affect the
probability of a break.
b. There is no or minimal effect on the consequences of analyzed
accidents due to deletion of the automatic isolation on high
temperature leak detection in the main steam line tunnel or due to
increasing the leak detection differential temperature setpoint and
allowable values to detect a 100 gpm steam leak from a crack in a
main steam line. The worst case accident corresponding to main steam
lines outside of the reactor vessel and primary containment boundary
is a main steam line break, which bounds the dose consequences of
any size steam leak less than a full break. Also, a 200 gpm steam
leak results in a calculated offsite dose within the annual whole
body dose limit and the radioiodine release limit per 10 CFR 50
Appendix I, if detected and isolated within several weeks.
(2) Create the possibility of a new or different kind of
accident from any accident previously evaluated because:
The purpose of the main steam line isolation is based on leak
detection and automatic isolation for leakage in the main steam line
tunnel downstream of the outermost isolation valve. This change
maintains this capability with only the leak detection based on high
differential temperature in the steam line tunnel. Also, the primary
containment isolation logic for main steam line leak detection
isolation on high differential temperature remains the same. Thus no
new or different accident is created.
(3) Involve a significant reduction in the margin of safety
because:
The increased setpoint for differential temperature leak
detection for automatic isolation of the main steam lines due to a
steam leak outside of the primary containment is based on
calculated/analyzed response to a steam leak [that is] small
compared to the leak from a critical crack. The leak detection
isolation logic remains single failure proof. The previous
evaluation of diversity of isolation parameters considered the
ambient temperature and differential temperature isolations as one
parameter in Table 5.2-8 of the LaSalle [Updated Final Safety
Analysis Report] UFSAR. The deletion of leak detection isolation of
the main steam lines based on high ambient temperature in the main
steam line tunnel is acceptable, because the differential
temperature isolation has been analyzed to detect and isolate the
main steam lines based on bounding inlet air temperatures.
Therefore, the Main Steam Line High flow, vessel low level, and the
differential temperature instruments maintain adequate diversity of
isolation parameters without main steam line tunnel high
temperature.
The differential temperature leak detection for the main steam
line tunnel depends on normal ventilation flow to detect leakage.
Therefore, the trip function will be declared inoperable upon loss
of or shutdown of normal ventilation. The Technical Specifications
currently allow the main steam tunnel high temperature and high
differential temperature isolation channels to be inoperable for up
to 4 or 12 hours during the performance of specified required
surveillances. The 12 hours allowed outage time is currently for an
18 month surveillance requirement. The addition of allowance for up
to 12 hours allowed outage time to recover normal ventilation
following an unplanned loss of normal ventilation is reasonable,
since the time is small compared to the time frame over which a pipe
crack grows. Also, supplemental monitoring of water collection sumps
and area temperature in the main steam line tunnel provides
heightened awareness of operators to detect leakage in the main
steam line tunnel during the time normal ventilation is not
available. The planned shutdown of normal ventilation is currently
allowed for up to 4 hours by the Technical Specifications. The
unplanned loss of normal ventilation is expected to be less than two
times per cycle upon completion [of] design changes to make the
isolation logic power supply D.C. instead of A.C. through motor
generator sets.
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.
[[Page 7283]]
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 March 28, 1996, 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 Jacobs Memorial Library, Illinois Valley
Community College, Oglesby, Illinois 61348. 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, 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 Robert A. Capra: 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 Michael I. Miller,
Esquire; Sidley and Austin, One First National Plaza, Chicago, Illinois
60603, 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 January 18, 1996, 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 Jacobs Memorial Library, Illinois
Valley Community College, Oglesby, Illinois 61348.
Dated at Rockville, Maryland, this 21st day of February 1996.
For the Nuclear Regulatory Commission.
M. David Lynch,
Senior Project Manager, Project Directorate III-2, Division of Reactor
Projects--III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 96-4343 Filed 2-26-96; 8:45 am]
BILLING CODE 7590-01-P
