ML20066E680
| ML20066E680 | |
| Person / Time | |
|---|---|
| Site: | Catawba  |
| Issue date: | 01/10/1991 |
| From: | Martin R Office of Nuclear Reactor Regulation |
| To: | |
| Shared Package | |
| ML20066E681 | List: |
| References | |
| NUDOCS 9101220169 | |
| Download: ML20066E680 (8) | |
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UNITED STATES NUCLEAk REGULATORY COMMIS$10N DUKE POWER COMPANY I
DOCKET h05. 50-413 AND $0-414 h0TICE OF_ CONSIDERATION OF ISSUANCE OF AMENDMENTS TO FACILITY OPERATING LICENSES AND PROPOSED NO SIGNIF] CANT HAZARDS CONSIDERATION DETERMINATION AND OPPORTUNITY FOR HEARING 2
T!.e U.S. Nuclear Regulatory Commission -(the Comission) is considering issuance of amendments to Facility Operating License Not,. hPF-35 a:.3 kPF-52 4
issued to Duh Power Comptny (the licensee) for operation of Catawb? Nuclear i
Statici., Units 1 and 2, located in York County, $0uth Carolina.
The preposed amendments would provide the licenset with an alternative other tha3 pluggirg for handl1hg defective steam gene:ator tubes. The amendhients wcid :llo? the option 01 using the B6bcock & Wilcox (B&W) Recirculating $tcam Ger,4rator kinetic Sleeve Qualification tube repair process as described in B&W Topical Report BAW 2045(P)-A. The licensee states that the topical report received NRC approvbi for such an application on January 4, 1990.
The amendments would involve changes to Surveillance Requirement 4.4.5, as identified in the application, to reflect the inclusion of sleeving in the surveillance acceptance criteria, to allow sleeving as an alternate to plugging tubes that exceed the repair liniit, to reflect repaired tubes in the reporting requiren.ents and in the Bases.
Before i n uance of thE proposed licanse amendments, the Commission will have n.ade findings required by the Atomic Energy Act of 1954, at amended (the Act) anc the Comminion's regulations, l
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The Comission has made a proposed determination that the request for ariendments involves no significant hazards consideration. Under the Commission's regulations in 10 CFR 50.92, this meent, that operation of the facility in i
accordance with the proposed araendments woulo not (1) involve a significant increete in the probebility or consequences of an accident previously evaluated; or (2) create the possibility of a new or different kind of accident from any accir%nt previously evaluated; or (3) involve a significant reduction ib a mr.rgir, cf safety.
/,5 requirec by 10 CFR 50.91(a), the licensee has provided tht following anal" sis about thc issue of no significant hazards consideration:
Operation of Catewba in acccroance with the propoted an.endment would not involve a significant increase in the probability or consequences 4
of an tccident previously evaluated.
Considering the function of the sittve, the principal accident associcted with this amenda,ent is the steam generator tube r F.ure accident.
The steam generator sleevt has been anclyzed and 6 ted to the cperating and design conditions of the original tube as docurented in Topical Report BAW-2045(P) A.
The Topical Report contains the design verification results fron,the analysis ad confirmatory testing performea on the sleeve. The probability or seg ur.ces of this previously evaluated accident does not involve e l
gnificant increase since the sleeve meets the original tube desigr, conditions and the structural integrity of the tube is maintained by tht sleeving process, and surveillance requirements.
The-sleeve is_less susceptibic to the identified stress corrosien failure mechanisms of the original tube because of the B&W specified installation process and the use of improved material (Alloy Inconci 690); therefore, the potential for primary to secondary leakage is also reduced by the addition of a steam generator tube sleeve. The continued integrity of the-sleeve will be verified by TS inspection requirements and the_ sleeve will be plugged in accordance with TS$, if necessary.-
. Operation of Catawba in accordance with the proposed amendment would not create the possibility of a new or different kind of accident from any accident previous 1) evaluated. The purpose of the sleeve is to repair a defective steam generator tubc to maintein the functicn and integrity of the tube as oppcsed to plugging and removing the tube from service.
The sleeve functions.in essentially the same manner as the original tube and has been analyzed and tested for steam generator design conditions.
The sleeve is less susceptible to the identified stress corrosion failure mechanisms of the original tube beccuse of the B&W specified installatien
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1 process and the use of improvec material (Alloy Inconel 690); therefore, the potential for primary to secondary leakage is also reduced by the addition of a steam generator tube sleeve.
The continued integrity of the slette will be verified by TS inspecti0n requirements and the sleeve will be plugged in accordance with 155, if necessary.
Repairing e steam generator tube to a serviceable ccncition utilizing the proposed sleeve-process dots not create the possibility of a new or different type of accident since the sleeve is a passive component with postulated 1 allures that are similar to the original tube.
Operatior a Catawba in accorcance with the proposed arr.endment would not involvt a vignificant reduction in a margir, cf safety.
The structure 1 integrity of the tube is maintained by the installation of the sleeve and 1
the sleene/ tube weld. The potential for primary to_ secondary leakage is-
-l reduced by tht, addition of the steam generator tube $1eeve. Tht sleeve is made cf Alloy 690 and is not subject to the same failure mechanisms of the original tube.
TheCatawbeLOCALLosscfCoolantAccident)analysisinChapter15ofthe FSAR takts into acccunt the effect of plugged tubes on primary coolant fitw.
The LOCA analysis assumes a worst case where 10% of the tubes i
art plugged. The effects of sleeve installation (versus tube plugging) on steam generator performance, heat transfer, flow restriction, and steam generation capacity were analyzed ano described in.the B&W Topical Report.
The results show that olugging one tube is equivalent to the htat transf er reduction of sleeving 48 tubes, the primary ficw reduction of sleeving 20 tubts, and the loss of steam generation cf capacit) of sleeving 40 tubes, in sumary, the tube sleeving does not result in a reduction cf the margin assumed in the LOCA analysis since it is bounded by the limits for tube plugging.
The Cou.ission's staff has reviewed the licensee's analysis, and based on this revitt, it-appears that the three stancards of 10 CFR 50.g2 are satisfied.
I Therefore, based on the above considerations, the Comission has made a proposed determination that the amendment request involves no significant hatards consideration.
The Comission is seeking public coments on this proposed determination.
Any coments received within 30 days af ter the date of publication of this notice will bc considered in making any final determination. The Comission will not normally make a final determination unless it receives a request for a hearing.
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I Written coments may be submitted by mail to the Regulatory Pub 11utions Branch. Division of Freedom of Information and Publications Services, Offs'ce of Adioinistration, U.S. Nuclear Regulatory Comission, Washington, DC 20565, and should cite the publication cate and page number of this FEDERAL REGISTER l
notice. Written coments may also be delivered.to Room P-223, Phillips Building, 7920 herfolk Avenue, Bethesda, Maryland, f rom 7:30 a.m. to 4: 15 p.m.
Copies of j
written comments received niay be examined at the NRC Public_ Document Room, the 1
Gelit6n building, 2120 L Street, NW., Washington, DC.
The filing of requests for hearing and petitions for leave to intervene is discussed below.
4 By February 19, 1991, the licensee may file a request for a hearing with respt.ct to issuance of the amendnients to the subject f acility operating licenses and any person whose interest may be affected by this proceedinr, and who wishes to particip6te as a party in the proceeding must file a written petition _for leave to intervene. Request for a hearing and petitions for leavc to intervene shall be filed in accordance with the Comissiot.*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 Comission's Public Document Room, the Geln.an Building, 2120 L Street, NW.,-Washington, DC 20555 and at the Local Public Document Room located at the-York County Library, 138 East Black Street, Rock Hill, South Carclina 29730.
If a request for a hearirs or petition for leave to intervene is f11cd by the above date, the Comission or an Atomic Safety and Licensing Board, designated by the Comission or by the Chairman of the Atomic-Safet) and Licensing Boaro Panel, will rule on the request and/or petition ano the Secretary or the designated Atomic Safety and Licensing Board will issue a notice of hearing or an appropriate order.
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- n 5-r As required by 10 CFR %?.714, a petition for leave to intervene shall 6tt forth with particularity the interest of the petitioner in the proceeding, and how thet interest niay be affected by the results of the proceeding.
The petition should specifically explain the reasons why intervention shculd be permitted with particular reference to the following factors:
(1) the r,ature of the petitioner's right under the Act to be nicde party to the proceeding:
(1) the naturt and extent of the petitierer's property, financial, or other i
intercstintheproceedingsand(3)-thepossibleeffectofanyorderwhich n.ay 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 petiticr without requesting leeve of the Board up to fifteen (15) cays 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 fifteen (15) days prior to the first prehearing conference i
l scheduled in the proceeding, a petitioner shtli file a supplement to the petition j
to intervene which must include a list of the contentions which are sought to be litigateo 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 l
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 wa w-e e
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i 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-genuint oispute exists with the applicant on a material issue of law or fact.
1 Contentions shall be limited to matters within the scope of the amendments
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I under consideration.
The contention must be one which, if proven, would ehtitle the petitioner to relief. A petitioner who fails to file such a l
supplement which satistles these requirements with respect to at _least one contention will not be permitted to participate as a party.
j Those permitted te-intervene become parties to the proceeding, subject to any liniitations in the order granting leave to intervene, and have the opportunity to participate fully in the conduct of the hearing, including the j
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 hela.
If the final determination is that the recuest for amendments involves no significant hazards consideration, the Conaission may issue the amendments and l
make them effective, notwithstt9 ding the request for a-hearing. Any hearing held would take place after issuance of.the. amendments.
if a f1nci determination is that the amendments involve a significant hazerds consideration, any hearing held would take place before the issuance of any n.cndment.
Normally, the Connission will not-issue the amendments until the expiration of the 30 day notice period.
However, should circumstances change during the notice period such that f ailure to act in a timely way would result, for exunple, in derating or shutdown of the f acility, the Comission may issue the license-I
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amendments before the expiration of the 30 day notice period, provided that its l
final determination is that the amendments involve no significant hazaros consideration. The final determination will consider all public and State comments received.
Should the Comission take this action, it will publish a notice of issuance and provide f or opportunity for a hearing af ter issuance.
The Comission expects that the need to take this action will occur very intrequently.
A request f or a hearir.p or a petition f or leave to intervene must be filed with the Secretary of the Comission,1.L5. Nuclear Regulatory Comission, Withington, DC 20555, Attention: Cocketing and Services Branch, or may be delivered to the Comission'b Public Document Room, th(. Gelman Building, 2120 L Street, NW., Wcshington, DC, by the above date.
Where petitions are filed i
during the last ten (10) dcyb of the notice period, it is requested that tN.
petitioncr promptly se inform the Commission by a toll-free telephone call'to l
Western Union at 1-(800)3256000 (in Missouri 1-(600)342-6700).
The Western Union operator should be given Datagram Identification Number 3737 and the following nusage addressed to David B. Matthews: (petitioner's-name and telephonc number), (dete petition has mailed), (plant nanie), and (publication cate and page number of this TEDERAL REGISTER notice). A copy of the petition should 61so be sent to the Office of the General Counsel, U.S. Nuclear Regulatory Comission, Washington, DC 20555, and to Mr. Albert Carr, Duke Power Company, 422 South Church Street, Charlotte, korth Carolina l'8242, attorney for the licensee.
Nontimely filings of petitions for leave to intervene,-amended petitions, l
supplemental petitions and/or requests for hearing will not be entertained absent a determination by the Commission, the presiding officer or the Atomic
6-Safety and Licensing Board that the petition and/or request should be granted baseauponabalancingofthefactorsspecifiedin10CFR2.714(a)(1)(i)-(v) and 2.714(d).
For further detail!, with respect to this action, see the applicatior, for amendment datec December 19, 1990, which is available for public inspection at the Commission's Public Document Room, the-Gelman Building, 2120 L Street, NW., hashington, DC 20555 and at the Local Public Docunient Room loceted at the York County Library,~138 East Black $treet, Rock Hill, South Carolina 29730.
j Dated at Rockville, Maryland, this 10th day of January,1991.
FOR THE NUCLEAR REGULATORY COMMIS$10N l
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h e t E. Martin, Senior Project Manager Project Directorate 11-3 Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation l
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