[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