ML20215L980

Forwards Byron Nuclear Plant Essential Svc Water Cooling Tower Test Plan Preliminary Evaluation, Ltr Rept Based on Presentation to NRC on 870513.Rept Completes Work Scope Requirements of Task 4-9 (TACs 64944 & 64945)

ML20215L980
Person / Time
Site:	Byron
Issue date:	05/22/1987
From:	Obenchain C EG&G IDAHO, INC., IDAHO NATIONAL ENGINEERING & ENVIRONMENTAL LABORATORY
To:	Carrington M Office of Nuclear Reactor Regulation
Shared Package
ML20215L983	List: ML20215L980 ML20215L990
References
CON-FIN-D-6023 OBEN-73-87, TAC-64944, TAC-64945, NUDOCS 8706260235
Download: ML20215L980 (2)

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/NEA Idaho National Engineeriny Laboratory May 22, 1987 Mr. Mayo Carrington, Project Manager Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission '

Washington, D. C. 20555 TRANSMITTAL OF BYRON ESW COOLING TOWER TEST PLAN EVALUATION LETTER REPORT

- Oben-73-87 Ref: INEL Technical Assistance to the Office of Nuclear Reactor Regulation, " Review of Plant-Specific Licensing Actions for Operating Reactor Issues" (FIN D6023), Task 4-9

Dear Mr. Carrington:

In accordance with the above reference, INEL is providing technical assistance to the Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, in the evaluation of plant-specific licensing actions.

Enclosed is the letter report documenting the Byron Essential Service Water (ESW) cooling tower (CT) test plan preliminary evaluation based on Byron's plan presentation to NRC in Bethesda on May 13, 1987. The conclusion of this preliminary evaluation is that the CT tests planned will provide more than adequate data for evaluating the cooling tower's capability to reject the design (accident) heat load at the design environmental conditions. The tests planned are significantly more extensive than and as accurate as the test required by the Cooling Tower Institute (CTI) Design Specification for acceptance testing new cooling towers.

The Byron CT test plan presented includes obtaining enough data points

(>20) to allow the CT design curve to be developed for this specific CT.

The CT manufacturer normally provides these curves and the slope of thern is based on their knowledge of their CT design but has only one data point (the acceptance test) to verify it is valid for this CT. Therefore, the slope of the CT performance curve is normally never verified for specific 1

8706260'235 B70522 4 ADOCK 0500 gDR Idaho Fars, ID 83415

[EGcG a.no.ene. P.O. Box 1625 .

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Mr. Mayo Carrington May 21, 1987 Oben-73-87 Page 2.

-1 cts. Byron's proposed CT testing and expected data reporting goes significantly beyond this " normal" CT capability verification.

A Byron site visit during the CT testing would be helpful to obtain ,

first-hand information on how the measurements are-taken and the data .

handled to assure valid CT test results. -N. E. Pace ~is also planning to '

make. time available to review Byron's test report.When it is submitted, as. l informally requested. lThis service can be provided without significant '

delays, if it can'be scheduled a month or so..in advance.

The current Byron plant operating restrictions based on wet bulb ,

temperature (WBT) seem to be unnecessary. The CT (3 bays) will dump the '

accident heat load.at the 78 F design' wet bulb temperature and design' .

air and water flow rates, but the cold water temperature might increr.se "

slightly above its. design value for a'short time (~10 min) (this-is based on their current test results). The large water volume in the CT basin will prevent that higher-temperature water from reaching the equipment being cooled by the ESW system by its large heat capacity.

The enclosed letter report completes the work scope requirements of Task 4-9 (TAC No. 64944 and 64945). .

Very truly yours,

~

C. F Obenchain,-Manager NRR & I&E Support Unit 1 NGP:ggo l

Enclosure:

As Stated cc: G. B. Staley, NRR/ESGB (4)

J. O. Zane, EG&G Idaho, Inc. (w/o Encl . )

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