ML19320A163
| 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: |
| References | |
| 1-127-19, NUDOCS 8004210466 | |
| Download: ML19320A163 (3) | |
Text
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i Mr. D. K. Davis Little Rock, Arkansas
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- ssentPTicN 1 ENC:.OsuRE LJcense No. DPR-51 Appl for Amend: tech specs propcsed change concerning parameter changes and modifications required for Cycle 3 operation..w/att supplementary info. in the l
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Director of Nuclear Reactor Regulation I
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Subject:
Arkansas Nuclear One - Unit 1 Docket No. 50-313 License No. DPR-51 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
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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
@dwn Amendment No. 21