ML19320A163

Forwards Proposed Change to Tech Spec 3.5 Re Parameter Changes & Mods Required for Cycle 3 Operation & B&W Reload Rept as Suppl Info.Requests Approval of Proposal Prior to Second Week in Mar

ML19320A163
Person / Time
Site:	Arkansas Nuclear
Issue date:	12/28/1977
From:	Rueter D ARKANSAS POWER & LIGHT CO.
To:	Desiree Davis Office of Nuclear Reactor Regulation
Shared Package
ML19320A164	List: ML19320A163 ML19320A167
References
1-127-19, NUDOCS 8004210466
Download: ML19320A163 (3)

Text

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Donald A. Rueter 12/29/76 .

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ssentPTicN 1 ENC:.OsuRE LJcense No. DPR-51 Appl for Amend: tech specs propcsed change concerning parameter -

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. 3 operation..w/att supplementary info. in the

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Director of Nuclear Reactor Regulation I ATIN: Mr. D. K. Davis, Chief .l?-n ff i operating Reactor Branch #2

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Subject:

Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 ,

g5{fl Proposed Technical Specifications (File: 1511.1)

Gentlemen:

Enclosed please find a proposed change to the Arkansas Nuclear One-Unit 1 Tec!'nical Specifications for your review and approval. This proposal was pre ,ared by-the Nuclear Power Generation Division of Babcock and Wilcox to incorporate those parameter changes and modifications required for Cycle 3 operation. Three copies of the Arkansas Nuclear One-Unit 1, Cycle 3 Reload Report as prepared by Babcock and Wilcox is attached as supplementary information.

Presently, the second refueling outage for Unit 1 is scheduled to begin January 28, 1978, and continue for approximately 8 weeks. Therefore, we are requesting that this proposal be approved and returned no later than the second week in March in order to allow time for implementation prior to Cycle 3 startup. '

If we may be of any further assistance in this regard, please contact us.

Very truly yours, Ad*

' onald A. Rueter

/ Director, Technical S Environmental Services DAR:JTE:nf Attachments

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Using a local quality limit of 22 percent at the point of minimum DNBR as a basis for curve 3 of Figure 2.1-3 is a conservative criterion even though the quality at the exit is higher than the quality at the point of minimum DNBR, The DNBR as calculated by the BAW-2 correlation continually increases from point of minimum DNBR, so that the exit DNBR is always higher and is a function of the pressure.

The maximum themal power for three pump operation is 85.6 percent due to a power level trip produced by the flux-flow ratio (74.7 percent flow x 1.060 79.1 percent power) plus the maximum calibration and instrumentation error.

The maximam themal power for other reactor coolant pump conditions is pro-duced in a similar manner.

For each curve of Figure 2.1-3, a pressure-temperature point above and to the left of the curve would result in a DNBR greater than 1.3 or a local quality at the point of minimum DNBR less than 22' percent for that particular reactor coolant pump situation. Curves 16 2 of Figure 2.1-3 are the most restrictive because any pressure / temperature point above and to the left of this curve will be above and to the left of the other curve.

PIFERENCES (1) Correlation of Critical Heat Flux in a Bundle Cooled by Pressurized Water, BAW-10000A, May, 1976. .

(2) FSAR, Sect ion 3. 2.3.1.1.c

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Amendment No. 21