ML20237C385

Application for Amend to License DPR-46,revising Tech Specs to Authorize Use of Fuel Assembly & Control Blade Lead Test Assemblies Subj to Prior NRC Written Approval.Fee Paid

ML20237C385
Person / Time
Site:	Cooper
Issue date:	12/14/1987
From:	Kuncl L NEBRASKA PUBLIC POWER DISTRICT
To:
Shared Package
ML20237C388	List: ML20237C385 ML20237C568
References
NUDOCS 8712210293
Download: ML20237C385 (5)

Text

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Nebraska Public Power District * "'T$obbfbT""'"

December 14, 1987 U.S. Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

Subject:

Proposed Change No. 53 to Technical Specifications Cooper Nuclear Station NRC Docket No. 50-298, DPR-46' In accordance with the applicable provisions specified in 10CFR50, Nebraska Public Power District requests that Technical Specifications for Cooper Nuclear Station (CNS) be revised to allow 'use of fuel assembly and control blade Lead Test Assemblies subject to prior written NRC approval.

A discussion and the applicable revised Technical Specification page are contained in Attachment 1. The modifications to the Technical Specifications within this proposed change have been l evaluated with respect to the requirements of 10CFR50.92. The results of the evaluations are also included in the attachment.

This proposed change incorporates all amendments to the CNS Fac.ility Operating License through Amendment 112 issued October 27, 1937. By copy of this letter and attachment the appropriate State of Nebraska official is being notified in accordance with 10CFR50.91(b).

This change has been reviewed by the necessary Safety Review Committees and payment of $150 is submitted in accordance with 10CFR170.12.

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Page 2 December 14, 1987 In addition to the signed original, 37 copies are also submitted for your use. Copies to the NRC Region IV Office and the CNS Resident Inspector are also being sent in accordance with 10CFR50.4(b)(2).

Should ycu have any questions or require additional information, please contact me.

Sincerely,

,d L. G. Kuncl Vice-President - Nuclear LGK/grs:mh12/2 Attachment cc: H. R. Borchert Department of Health State of Nebraska NRC Regional Office Region IV Arlington, TX NRC Resident Inspector Office Cooper Nuclear Station l

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Page 3 STATE OF NEBRASKA)

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L. G. Kuncl, being first duly sworn, deposes and says that he is an authorized representative of the Nebraska Public Power District, a public corporation and political subdivision of the State of Nebraska; that he is duly authorized to submit this request on behalf of Nebraska Public Power District; and that the statements contained herein are true to the best of his knowledge and belief.

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/L.G.Kuncl S bscribe sence and sworn to before me this M day lml)O 7}l Ni k NGIARY PUE)t.lc /

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l Attachment 1 Revised Technical Specifications for Lead Test Assemblies Revised Page: 217

Reference:

1) Letter, T. A. Ippolito (NRC) to R. E. Engel (General Electric),

" Lead Test Assembly Licensing," September 23, 1981.

l Lead Test Assembly (LTA) programs are a means of testing new mechanical, hydraulic, or reactivity designs in search of improvements in safety and operational flexibility for fuels and control rods. Reference 1 describes the licensing provisions acceptable to the NRC to provide a simplified procedure for approval of LTA's. Key elements of this procedure were (a) as long as the analysis of the LTA's used approved metbods and met approved criteria, it would be concluded that no unreviewed safety questions exist and (b) a utility would provide a description of the LTA's and a statement regarding the applicability of the reload Licensing Topical Report in an information letter to the NRC.

The District plans to install several fuel assembly and control rod LTA's in the core this upcoming refueling outage as part of General Electric's Test Program. By revising the Cooper Nuclear Station (CNS) Technical Specifications to allow use of LTA's subject to prior written NRC approval, the need for a specific license amendment is avoided for subsequent LTA's that will be tested at CNS in the future. This will avoid use of NRC staff and District resources in pursing the license amendment process to obtain LTA approval. By follo'ing w the guidance of Reference 1, approval will be requested via an information letter to the NRC that discusses that particular LTA program, obj ectives , analysis, and applicability to the reload Licensing Topical Report.

The District requests that page 217 of the CNS Technical Specifications be revised to incorporate Section 5.2.C to allow use of LTA's in conjunction with vendor test programs subject to prior written approval from the NRC.

Evaluation of this Revision with Respect to 10CFR50.92 A. The enclosed Technical Specification change is judged to involve no significant hazards based on the following:

1. Does the proposed license amendment involve a significant increase in the probability or consequences of an accident previously evaluated?

Evaluation:

The proposed amendment would allow the use of fuel assembly or control blade LTA's of different design in the core subject to prior written NRC approval. The LTA's will be evaluated using approved methods meeting approved criteria. Prior approval by the NRC is required before plant operation can commence with LTA's installed in the core. These reviews will establish that the LTA's will not involve a significant increase in the probability or consequences of an accident previously evaluated.

2. Does the proposed license amendment create the possibility for a new or different kind of accident from any accident previously evaluated?-

Evaluation:

The proposed amendment will allow LTA's of a different design to be used in the plant subject to prior NRC approval. The LTA's will.

therefore have prior NRC review which will include an evaluation and determination that the possibility for a new or different kind of accident is not created.

3. Does the proposed amendment involve a significant reduction in a j margin of safety? )

Evaluation:

The proposed amendment will allow LTA's of a different design to be used subject to prior NRC review and approval. The LTA's will be analyzed using approved methods and will meet approved criteria to

. ensure there is no reduction in a margin of safety.

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