ML20023B527

Interim Deficiency Rept Re Itt Barton Class IE Transmitters Exhibiting Thermal Nonrepeatability.Initially Reported on 821210.Since Errors within Safety Analysis Limits,No Setpoint Changes Required

ML20023B527
Person / Time
Site:	Mcguire
Issue date:	04/28/1983
From:	Tucker H DUKE POWER CO.
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
References
10CFR-050.55E, 10CFR-50.55E, NUDOCS 8305050153
Download: ML20023B527 (2)

Text

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f DUKE POWER GOMPANY

} P.O. HO x 3 0189 CHAMLOTrE, N.C. 28242 HALB. TUCKER TE R.E NE i

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!- Mr. James P. 0'Reilly, Regional Administrator. g 3,3 U..S. Nuclear Regulatory Commission- 3 N Region II ' ~~

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101 Marietta Street, NW, Suite 2900 ';,,3 Atlanta, Georgia 30303 ., t( a "co E ;.)

-Re: McGuire Nuclear Station, Unit 2 .. Z Docket No. 50-370 w ,

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Dear Mr. O'Reilly:

a My December-10, 1982 letter submitted (pursuant to 10 CFR 50.55e) an interim Significant Deficiency report (SD-370/82-06) concerning ITT Barton Class IE

! transmitters exhibiting thermal non-repeatability. Since our last report dated March 31, 1983, Westinghouse has received additional information from Barton regarding the thermal non-repeatability errors previously reported by Barton.

Westinghouse has been actively reviewing this data in order to substantiate Barton's published information concerning these errors. Presently, based on a statistical evaluation of the Barton error data by Westinghouse, Duke and West-inghouse' conclude that the errors are within the limits of the safety analysis 4' and therefore no setpoint changes are required. This conclusion is based on a review of'the Barton transmitters used for steam generator level (narrow range) 4, which have the least margin between the setpoint value and the value assuned in

the safety analysis for low steam generator level. The review revealed 'nat the

!. maximum errors during accident conditions for all McGuire Unit 2 Barton trans-l' mittere should be less than the original error allowance assumed in the accident analysis.- This is based on taking credit for polarity of the dynamic temperature error, and the actual temperature compensation and the actual temperature condi-tions at McGuire. Errors at lower temperatures (130 F) will most likely be I increased slightly but should be absorbed by the margin in the safety analysis.

i Westinghouse has. stated and we concur that this. evaluation, based on current

'information, provides sufficient justification for unit startup and operation.

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] The Westinghouse generic evaluation of this issue is still ongoing and involves more testing by Barton. Duke is following the progress of the generic evaluation and.will provide a' followup response concerning this issue as soon as data is

, available.

Very truly yours, C . e/ /$ ' < -

Hal B. Tucker PBN:jfw

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James P. O'Reilly April 28, 1983 Page 2 cc: Director Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C. 20555 Mr. W. T. Orders NRC Resident Inspector McGuire Nuclear Station