ML20072V550
| ML20072V550 | |
| Person / Time | |
|---|---|
| Site: | Sequoyah  |
| Issue date: | 09/13/1994 |
| From: | Labarge D Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20072V552 | List: |
| References | |
| NUDOCS 9409200032 | |
| Download: ML20072V550 (8) | |
Text
y-UNITED STATES NVCLEAR REGULATORY COMMISSION SE0VOYAH NUCLEAR PLANT UNITS 1 AND 2 DOCKET NOS. 50-327 AND 50-328 LOTICE OF CONSIDERATION OF ISSUANCE OF AMENDMENT TO FACILITY OPERATING LICENSE. PROPOSED NO SIGNIFICANT HAZARDS CONSIDERATION DETERMINATION. AND OPPORTVNITY FOR A HEARING The U.S. Nuclear Regulatory Commission (the Commission) is considering issuance of amendments to facility Operating License Nos. DPR-77 and DPR-79 issued to the Tennessee Valley Authority (the licensee) for operation of the Sequoyah Nuclear Plant, Units 1 and 2, located in Soddy Daisy, Tennessee.
The proposed amendments, submitted by the licensee's letter dated September 8,1994, would incorporate a clarification to separate the portion of the steam generator tubing from the end of the tube up to the start of the tube-to-tubesheet weld from the remainder of the tube for the purposes of sample selection and repair when defects are found in this section of a steam generator tube.
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 hat 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 amendments would not (1) involve a significant 1
ENCLOSURE 940920{K132 940913 i
PTNt AD(NCK 05(X)D327 p
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2-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 i
has provided its analysis of the issue of no significant hazards consideration, which is presented below:
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TVA has evaluated the proposed technical specification (TS) change and has determined that it does not represent a significant hazards consideration based on criteria established in 10 CFR 50.92(c). Operation of Sequoyah Nuclear Plant (SQN) in accordance with the proposed amendment will not:
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Involve a significant increase in the probability or t
consequences of an accident previously evaluated.
This change will clarify the requirements for indications found in the region of the steam generator (S/G) tube, which protrudes below the tubesheet.
This region of the tube does not affect the structural integrity of the reactor coolant system (RCS) pressure boundary, since it is not part of the pressure boundary. This revision will exempt this portion of the tube from being considered under the result and action required sections of Table 4.4-2 in SQN's TS.
Therefore, indications in this region will not require repairs and will not be used for the purpose of expanding the sample of tubes to be inspected under the. requirements of the TS.
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The condition described in this evaluation results'in tube integrity considerations commensurate with Regulatory Guide 1.121 criteria both analytically and empirically.
If the indications are hypothetically considered as cracks, the Row I tube end indications neither adversely affect S/G tube integrity or any other component, nor does the presence of the indications alter the function of the S/G or.any other crmponent. Continuing the hypothetical scenario, even if the crack propagated beyond the weld, the only consequence of an accident that could be caused by plant operation or by the occurrence of a faulted condition event with the tube end indications, ~would be negligible leakage from the primary to secondary system.
Such leakage is expected to be insignificant at both normal and faulted conditions.
Therefore, plant operation with the tube end indications present in the Row I tubes does not increase the. probability-of an analyzed accident such as a S/G tube rupture event,
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Create the possibility of a new or different kind of accident from'any previously analyzed.
Any hypothetical accident as a result of plant operation with the Row I tube end indications would be bounded by the consequences of a postulated S/G tube rupture. Therefore, this change does not create the possibility of a new or different kind of accident from any previously analyzed.
3.
Involve a significant reduction in a margin of safety.
The locations of the axial indications observed are below the tube-to-tubesheet weld.
Consequently, it is concluded that the axial indications do not affect the structural and leakage integrity of the primary pressure boundary. Should the indications be single or multiple axial cracks on the tube ends, the effect of crack propagation was evaluated Tube burst is precluded for cracks within the tubesheet by the constraint provided by the tubesheet.
Therefore,. crack lengths do not need to be limited by burst considerations and operating leakage limits are not required to detect crack lengths associated with the tube burst.
- However, primary to secondary leakage must.be shown to remain within acceptable limits during all plant conditions.
Leak-rate testing shows that such leakage would be negligible during all plant conditions.. Since the pressure boundary integrity, acceptable leak rate, and function'of. the S/G are not affected by the presence of the tube end indications, 4
the margin of safety is not reduced.
~1 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.
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The Commission is seeking public comments on this proposed-j
-determination. Any comments received within 30 days after the date of
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publication of this notice will be considered 'in making any final' dy determination.
Normally, the Commission will not issue the, amendment:until the
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. 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.
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. 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 S'ould the Commission take this all public and State comments received.
h 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 L 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.
i may be examined at the NRC Public Document Room, the Gelman Building,
.2120 L Street, NW., Washington, DC 20555.
The filing of requests for hearing and petitions for leave to intervene i
is discussed below.
By October 19, 1994, 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 i
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' i
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4 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 20555' and at the local. public document room located at the Chattanooga-Hamilton County Library, 1101 Broad Street, Chattanooga, Tennesee 37402.
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 i
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 facto s:
(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 E
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 mayl 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
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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 isste 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 suf ficient 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 pro:eeding, 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.
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If the final determination is that the amendment request involves no.
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Esignificant hazards consideration, the Commission may issue the amendment and j
y make it immediately effective, notwithstanding the request for a hearing. Any.
j hearing held would take place after issuance of the amendment.
If the final determination is that the amendment request involves a fa 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, ormaybedeliveredi.otheCommission'sPublicDocumentRoom,theGelman Building, 2120 L Street, NW., Washington, DC 20555, by the above date. Where l
c petitions are filed during the last 10 days of the notice period, it is b
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requested that the petitioner promptly so inform the Commission by a toll-free j
telephone call to Western Union at-1-(800) 248-5100.(in Missouri 1
i 1-(800) 342-6700). The Western Union. operator should.be given Datagram
-Identification Number N1023 and the following message addressed to Mr. Frederick-J..Hebdon: 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 J
the General Counsel, U.S. Nuclear Regulatory Commission, Washington, DC 20555, and.to General Ccur.cil, Tennessee Valley Authority, ET llH, 400L West Summit Hill Drive, Knoxville, Tennessee 37902, attorney for the licensee.
Nontimely filings of. petitions for le' ave to intervene, amended '
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~ petitions, ' supplemental petitions and/or requests for hearing will not-be entertained absent a' determination by the Commission, the' presiding officer or J
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.the presiding Atomic Safety and Licensing Board.that the petition and/orz
- request should be granted based upon a balancing of the factors specified in 10 CFR 2.714(a)(1)(1)-(v) and 2.714(d).
For-further details with respect to this action, see the application 1for 1
amendment dated September 8,1994, which is available for public inspection at.
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the Commission's Public Document Room, the Gelman Building, 2120 L Street, NW., Washington, DC 20555 and at the local public document room' located at.the l
Chattanooga-Hamilton County Library, 1101 Broad Street, Chattanooga, Tennesee 37402.
Dated at Rockville, Maryland, this 13th day of September 1994.
FOR THE NUCLEAR REGULATORY COMMISSION l
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W David E. LaBarge, Sr. Project Manager Project Directorate II-4 Division of Reactor Projects - I/II Office af Nuclear Reactor Regulation 4
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