ML20045E036

Application for Amends to Licenses NPF-35 & NPF-52,changing TS to Modify Requirements for Fuel Assemblies in Design Features Section of TS Per Suppl 1 to GL 90-02.New Rods,W/ Shorter Active Fuel Rod Length,Will Be Installed

ML20045E036
Person / Time
Site:	Catawba
Issue date:	06/17/1993
From:	Rehn D DUKE POWER CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML20045E037	List: ML20045E036 ML20045E039
References
GL-90-02, GL-90-2, NUDOCS 9307010015
Download: ML20045E036 (6)

Text

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. . I Duke Ibwer Company (803)M313000 Corawba Mxkar Stanon 4M0 Conc ord Rad

^ h4 SC2976

(  ; DUKEPOWER June 17, 1993 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555

Subject:

Catawba Nuclear Station, Units 1 and 2 Docket Nos. 50-413, 50-414 Proposed Technical Specifications Change Modify the Requirements for Fuel' Assemblies in the Design Features Section of Technical Specifications in Accordance with GL 90-02, Supplement 1 Gentlemen:

On July 31, 1992, the NRC issued Supplement 1 to Generic i Lettter 90-02, " Alternative Requirements for Fuel Assemblies in the Design Features Section of Technical Specifications". This change provides flexibility in the repair of fuel assemblies containing damaged and leaking fuel rods by reconstituting the assemblies. Catawba Nuclear Station has chosen to adopt-the model Technical Specification provided with Supplement 1.

Pursuant to 10 CFR 50.90, please find attached a proposed license amendment to facility operating licenses NPF-35 and NPF-52 for Catawba Nuclear Station Units 1 and 2, respectively.

This proposed Technical Specification (TS) revision contains the following proposed change:-

1. Modified requirements for " Fuel Assemblies" in the

" Design Features" section of TS in accordance with Generic Letter (GL) 90-02, Supplement 1 Attachment I provides a technical discussion , no significant hazards analysis, and environmental impact analysis supporting these proposed revisions. Attachment.II provides the proposed Catawba TS change.

Duke Power requests a timely review and approval of the proposed TS revision in view of the Catawba Unit 2 end of cycle 6 shutdown schedule which has a projected start date of May 26, 1994. Plans are being made to remove the rods and-VGnn, 0 wom.

9307010015 930617 PDR ADOCK 05000413 Q E

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U.S. NRC June 17, 1993

• Page 2 insert new rods with a shorter active fuel rod length during the Catawba end of cycle 6 refueling shutdown.

Pursuant to 10 CFR 50.91(b) (1) , a copy of this amendment request has been provided to the appropriate South Carolina state official.

Should there be any questions concerning this matter or if additional information is required, please call A.D.- Jones-Young at (704) 382-3154 or L.J. .Rudy at (803) 831-3084.

Very truly yours, hu - - -

D. L. Rehn, Vice President Catawba Site adj/CTSC2  :

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'U.S. NRC June 17, 1993 Page 3 xc: W/ Attachments S. D. Ebneter Regional Administrator, Region II R. E. Martin, ONRR R. J. Freudenberger Senior Resident Inspector (CNS)

Heyward Shealy,-Chief Bureau of Radiological Health and Environmental Control.

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, Page 4 D. L. Rehn, being duly sworn, states that he is Vice-President of Duke Power Company; that he is authorized on the part of said company to sign and file with the U.S. Nuclear. Regulatory Commission this revision to the Catawba Nuclear Station License Nos. NPF-35 and NPF-52; and that all statements and matters. set forth therein are true and correct to the best of his knowledge.

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D. L. Rehn, Site Vice-President Subscribed and sworn to before me this seventeenth day of June 1993.

l hrxk W0t m-Nopary Publig ty Commission Expires:

A la t!- 31 2600 3

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ATTACHMENT I DUKE POWER COMPANY CATAWBA NUCLEAR STATION Technical Discussion, No Significant Hazards and Environmental Analysis Technical Discussion The purpose of the proposed amendment request for Catawba Nuclear Station is to:

1. Modify the requirements for " Fuel Asssemblies" in the " Design Features" section of TS in accordance with GL 90-02, Supplement l 1 The basis for this change is provided in the following paragraph.

The re.quirements for fuel assemblies specify the quantity of fuel assemblies, the active fuel rod length and the number of fuel rods per assembly. Flexibility to deviate from the number of fuel rods per assembly and active fuel rod length is desirable to permit timely removal of fuel rods that are found to be leaking during a refueling outage or are determined to be probable sources of future leakage. This improvement in the licensee's fuel performance program will provide for reductions in future occupational radiation exposure and plant radiological releases.

No Significant Hazards Analysis 10 CFR 50.91 requires that the following analysis be provided concerning whether the proposed amendment request involves a significant hazards consideration as defined in 10 CFR 50.92.

Standards for determinatilon that an amendment request does not involve a significant hazards consideration are if operation of the facility in accordance with the proposed amendment would not: 1) ,

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' Involve a significant increase in the probability or consequences ,

of an accident previously evaluated; or 2) Create the possibility i of a new or different kind of accident from any previously - l evaluated; or 3) Involve a significant reduction in a margin of l safety.

1. Modify the requirements for " Fuel Assemblies" in the " Design Features" section of TS in accordance with GL 90-02, supplement 1

The proposed change to the requirements for " Fuel Assemblies" in the " Design Features" section of TS will not involve a significant increase in the probability or consequences of an accident previously evaluated because the modification merely provides' a broader blanket under which any future specific modifications to the plant or changes to its safety analysis may be performed, while still requiring that any such changes meet the same standards and criteria that they would have been subject to.

1 The creation of a new or different kind of accident from any previously evaluated accident is not considered a possibility because the change is administrative in nature and does not represent an actual modification to the plant or change to its safety analyses.

The margin of safety is maintained by adherence to other fuel related TB limits and the FSAR design bases. The change does not directly affect any safety system or the safety limits, and thus does not affect the plant margin of safety.

Accordingly, this proposed change does not involve a significant hazards consideration.

Environmental Impact Analysis The proposed TS amendment has been reviewed against the criteria of 10 CFR 51.22 for environmental considerations. The proposed amendment does not involve a significant hazards consideration, nor increase the types and amounts of effluents that may be released offsite, nor increase individual or cumulative occupational radiation exposures. The proposed amendment request is administrative in nature and therefore, meets the criteria given in 10 CFR 51.22 (c) (9) for a categorical exclusion from the requirement for an Environmental Impact Statement.

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