[Federal Register Volume 61, Number 177 (Wednesday, September 11, 1996)]
[Notices]
[Pages 47968-47971]
From the Federal Register Online via the Government Publishing Office [www.gpo.gov]
[FR Doc No: 96-23197]
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NUCLEAR REGULATORY COMMISSION
[Docket Nos. 50-295 AND 50-304]
Commonwealth Edison Company; 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
considering issuance of amendments to Facility Operating License Nos.
DPR-39 and DPR-48 issued to Commonwealth Edison Company (ComEd, the
licensee) for operation of the Zion Nuclear Power Station, Units 1 and
2, located in Lake County, Illinois.
The proposed amendments would remove the uncertainty term from the
specified distance and remove the footnote which specifies the time
frame it is applicable.
Before issuance of the proposed license amendments, the Commission
will have made findings required by the
[[Page 47969]]
Atomic Energy Act of 1954, as amended (the Act) and the Commission's
regulations.
The Commission has made a proposed determination that the
amendments requested involve 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:
1. The proposed changes do not involve a significant increase in
the probability of occurrence or consequences of an accident
previously evaluated.
The proposed change is to provide clarification as to how the F*
Distance is ensured at Zion Station. The associated footnote which
details the applicable timeframe is being deleted. The discussion
added to the Bases section of Technical Specifications will clarify
the application of eddy current uncertainty when sizing a new hard
roll region and when locating indications within the F* Distance.
These changes are administrative in nature and have no impact of the
probability or consequences of an accident.
Application of the F* Distance 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.
As previously discussed in the ComEd submittal (ComEd letter to
the NRC dated October 6, 1995, transmitting the Licensing Amendment
Request Modifying the F* Distance Definition for Zion Units 1 and
2), the proposed change will allow an F* Distance of 1.05 inches to
be applied to disposition steam generator tubes that are degraded in
the tubesheet roll transition region. The F* Distance specifies 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.
The Feedwater Line Break (FLB) accident was used as the limiting
event in the evaluation of the F* Distance. 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* Distance 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* Distance will not significantly increase
the consequences of any accident previously evaluated. The F*
Distance ensures 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* Distance, 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.
Application of the F* Distance will not affect the ability to
safely shut down the operating unit and/or mitigate the consequences
of an accident. Additionally, the proposed revisions will not
necessitate changes to plant operating procedures during normal
operation or the emergency procedures governing accident conditions
and plant recovery.
Since the proposed change only clarifies how the F* Distance is
ensured at Zion Station, the proposed change will not increase the
probability of occurrence or consequences 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* Distance.
As previously discussed in ComEd's submittal (ComEd letter to
the NRC dated October 6, 1995, transmitting the Licensing Amendment
Request Modifying the F* Distance Definition for Zion Units 1 and
2), the F* Distance 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* Distance ensures that
the structural integrity of the steam generator tube will be
equivalent to the original tube.
The proposed revised F* Distance definition is consistent with
the original analysis performed to justify the acceptability of the
F* Distance in dispositioning steam generator tubes with degradation
in the tube sheet region. Because the size of a new hard roll joint
will depend on the effective size of the mechanical roller used to
install the joint, no eddy current uncertainty need be considered.
For inspections following the new hard roll, the eddy current
uncertainty will not be required since Zion will repair all tubes
with indications in the mechanical roll region.
Therefore, it has been concluded that the proposed revision does
not create the possibility of a new or different type of accident is
created.
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*
Distance 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
[[Page 47970]]
can complicate steam generator tube inspection activities.
Application of the F* Distance 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* Distance 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
proposed revised F* Distance definition is consistent with the
original analysis performed to justify the application of the F*
criteria in the dispositioning of steam generator tubes with
degradation in the tube sheet region. The revision of the F*
Distance is administrative in nature.
Based on the above discussion it is concluded that the proposed
changes will not significantly reduce a margin of safety.
Based upon the preceding analysis it is concluded that the
proposed amendment does not increase the probability of an accident
previously evaluated, does not create the possibility of a new or
different kind of accident from that previously evaluated, nor
reduces any margin to plant safety. Therefore, this proposed
amendment does not involve a significant hazards consideration as
defined in 10 CFR 50.92.
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
amendments requested involve 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 amendments 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 amendments before the expiration
of the 30-day notice period, provided that its final determination is
that the amendments involve 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
Review and Directives Branch, Division of Freedom of Information and
Publications 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 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 October 11, 1996, the licensee may file a request for a hearing
with respect to issuance of the amendments 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 N. 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 amendments 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 amendments requested involve
no significant hazards consideration, the Commission may issue the
amendments and make them immediately effective,
[[Page 47971]]
notwithstanding the request for a hearing. Any hearing held would take
place after issuance of the amendment.
If the final determination is that the amendments requested involve
a significant hazards consideration, any hearing held would take place
before the issuance of any amendments.
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: 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 20555-0001, 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 amendments dated August 16, 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 Waukegan Public Library, 128 N.
County Street, Waukegan, Illinois 60085.
Dated at Rockville, Maryland, this 5th day of September 1996.
For the Nuclear Regulatory Commission.
Donna M. Skay,
Acting Project Manager, Project Directorate III-2, Division of Reactor
Projects--III/IV, Office of Nuclear Reactor Regulation.
[FR Doc. 96-23197 Filed 9-10-96; 8:45 am]
BILLING CODE 7590-01-P