[Federal Register Volume 60, Number 199 (Monday, October 16, 1995)]
[Notices]
[Pages 53648-53651]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 95-25539]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-295 and 50-304]
Commonwealth Edison Company 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 Nos.
DPR-39 and DPR-48 issued to Commonwealth Edison Company (the licensee)
for operation of the Zion Nuclear Power Station, Units 1 and 2, located
in Lake County, Illinois.
The proposed amendment would change the definition of the F*
distance in the Technical Specifications.
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
[[Page 53649]]
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 changes do not involve a significant increase in
the probability of occurrence or consequences of an accident
previously evaluated.
Application of the F* criteria to degraded steam generator tubes
will not affect any of the initiators or precursors of any accident
previously evaluated. Application of the proposed change will not
increase the likelihood that a transient initiating event will occur
because transients are initiated by equipment malfunction and/or
catastrophic system failure. The proposed change will allow an F*
criteria of 1.05 inches to be applied to disposition steam generator
tubes that are degraded in the tubesheet roll transition region. The
F* criteria specify a minimum length of tubing which must be free
from any indication of degradation. Below the F* Distance, any type
or size of indication, including complete circumferential through
wall cracking, will not impact the structural integrity of the tube
with respect to pull out forces during normal operation or accident
conditions, and does not significantly affect the leakage behavior
of the tube.
While the Zion [Updated Final Safety Analysis Report] UFSAR does
not specifically address the Feedwater Line Break (FLB) accident,
the FLB event was used as the limiting event in the evaluation of
the F* criteria. The FLB pressure differential of 2650 psi maximizes
the axial loading on the tube for pull out considerations and is
bounding. In addition, the close proximity of the tubesheet to the
tube will prevent tube rupture or collapse of the tube in the
tubesheet span. Because application of the F* criteria will ensure
that degraded tubes will provide the same structural integrity as an
original undegraded tube during normal operation and accident
conditions, the probability of occurrence of an accident previously
evaluated is not significantly increased.
Application of the F* criteria will not significantly increase
the consequences of any accident previously evaluated. The F*
criteria ensure that sufficient length of undegraded tube exists to
maintain structural integrity and preclude significant leakage. Due
to the proximity of the tubesheet to the tube, any leakage from
degradations below the F* Distance would be negligible and would be
well below the Technical Specification limits established for steam
generator leakage. Tube rupture as a result of indications below the
F* Distance is precluded because the tubesheet prevents outward
expansion of the tube in response to internal pressure.
The relationship between the tubesheet region leak rate at the
most limiting postulated accident conditions relative to that for
normal plant operating conditions has been assessed. For the
postulated leak source within the roll expansion, increasing the
differential pressure on the tube wall increases the driving head
for the leak; however, it also increases the tube to tubesheet
loading.
For a leak source below the F* Distance, the maximum assumed
pressure differential results in an insignificant leak rate relative
to that which could be associated with normal plant operation. This
is a result of the increased tube to tubesheet loading associated
with the increased differential pressure. Thus for a circumferential
indication within the roll expansion that is left in service in
accordance with the F* criteria, any leakage under accident
conditions would be less than that experienced under normal
operating conditions. Therefore, any leakage under accident
conditions would be less than the existing Technical Specification
leakage limit, which is consistent with accident analysis
assumptions.
Steam generator tube integrity must be maintained under the
postulated loss of coolant accident condition of secondary-to-
primary differential pressure. Based on tube collapse strength
characteristics, the constraint provided to the tube by the
tubesheet gives a margin between the tube collapse strength and the
limiting secondary-to-primary differential pressure condition, even
in the presence of circumferential or axial indications. The maximum
secondary-to-primary differential pressure during a postulated LOCA
is 1005 psid. This value is significantly below the residual preload
between the tubes and the tube sheet. Therefore, no significant
secondary-to-primary leakage would be expected to occur.
In addition, the proposed changes will not affect the ability to
safely shut down the operating unit and mitigate the consequences of
an accident because the proposed changes will not necessitate
changes to the emergency procedures governing accident conditions or
plant recovery.
An administrative change is also included which deletes a
footnote added for Unit 1 with Amendment 167. This footnote provided
temporary relief and is no longer applicable. Those proposed changes
will not increase the probability of occurrence or consequence of
any accident previously evaluated.
2. The proposed changes do not create the possibility of a new
or different kind of accident from any accident previously
evaluated.
The proposed changes to the Technical Specifications do not
involve the addition of any new or different types of safety related
equipment nor do they involve the operation of any equipment
required for safe operation of the facility in a manner different
from those addressed in the UFSAR. No safety related equipment or
function will be altered as a result of the proposed changes. Also,
the procedures governing normal plant operation and recovery from an
accident are not changed by the application of the F* criteria. The
F* criteria will allow the use of an alternate method to plugging or
sleeving to repair steam generator tubes with degradation in the
tubesheet region. The F* criteria ensure that both the structural
integrity and leak tight nature of the steam generator tube will be
equivalent to the original tube. Because the distance will be
reflective of the roller size, no uncertainty need be considered.
For subsequent inspections, the eddy current uncertainty will be
considered if new indications are discovered within the re-rolled
region. Since no new failure modes or mechanisms are introduced by
the proposed changes, no new or different type of accident is
created.
An administrative change is being proposed to remove a footnote
which is no longer applicable. This proposed changes will not create
the possibility of a new or different kind of accident from those
previously evaluated.
3. The proposed changes do not involve a significant reduction
in a margin of safety.
Plant safety margins are established through Limiting Conditions
for Operation (LCOs), limiting safety system settings, and safety
limits specified in Technical Specifications. There will be no
changes to the LCOs, limiting safety system settings, or the safety
limits as a result of the proposed changes. Application of the F*
criteria will allow degraded steam generator tubes to be repaired by
an alternative method to plugging or sleeving. Steam generator tube
plugging decreases the total primary reactor coolant flow rate and
heat transfer capability of the steam generator. While steam
generator tube sleeving only slightly reduces the reactor coolant
flow rate, large numbers of sleeves can have a measurable effect on
flow rate and can complicate steam generator tube inspection
activities.
Application of the F* criteria will allow a repair method that
will restore the integrity of degraded steam generator tubes and
will not adversely affect primary system flow rate or heat transfer
capability. Application of the F* criteria will preserve the heat
transfer capability of the steam generators and will maintain the
design margins assumed in the analyses contained in the UFSAR. The
alternate repair method will also be less complicated, faster, and
will reduce personnel occupational exposure significantly. Based on
the above discussion it is concluded that the proposed changes will
not significantly reduce a margin of safety.
The administrative change to remove a footnote which is no
longer applicable will not impact any 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
[[Page 53650]]
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 November 15, 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 Waukegan Public Library, 128 North County
Street, Waukegan, Illinois 60085. 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, Director, Project Directorate
III-2: 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 60690, 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
[[Page 53651]]
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 October 6, 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 Waukegan Public Library, 128 North County
Street, Waukegan, Illinois 60085.
Dated at Rockville, Maryland, this 10th day of October 1995.
For the Nuclear Regulatory Commission.
Clyde Y. Shiraki,
Project Manager, Project Directorate III-2, Division of Reactor
Projects--III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 95-25539 Filed 10-13-95; 8:45 am]
BILLING CODE 7590-01-P
