[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