ML19317E902

Summary of 740813 Meeting W/Util & B&W in Charlotte,Nc Re Differences Between Calculated & Measured Rod Worths & Other Physics Issues

ML19317E902
Person / Time
Site:	Oconee
Issue date:	08/22/1974
From:	Kopp L US ATOMIC ENERGY COMMISSION (AEC)
To:	Ross D US ATOMIC ENERGY COMMISSION (AEC)
References
NUDOCS 8001070702
Download: ML19317E902 (5)

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D. F. Ross, Chief, Core Per.?ormance Branch, L P. Check, Sontion leader, CPB, L THRU:

TRIP REPORT - VISIT TO DUKE POWER COMPANY I

i Company Enclosed is a sumary of a meeting held at Duke Power

[

I 13, 1974. An attendance j

in Charlotte, North Carolina on August I

l list is also enclosed.

['"E"wLunag

. Kopg, L. I. Kopp I

Core Performance Branch t

Directorate of Licensing i.

Enclosure:

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Heeting Sumary

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2.

Attendance List cc:

S. Hannuar P, Schroeder i

V. Stello Distribution:

Nichols Central Files

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R. Praley, ACRS (16)

CPB-Reading R. DeYoung L Reading t-R. Denise V. Moore D. Skovholt D. Muller K. Coller R. Tedesco R. Maccary H. Denton P-RP Branch Chiefs

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TR Branch Chiefs'

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4' TRIP REPORT - MEETING WITH DUKE POWER COMPANY & B&W A meeting was held on August 13, 1974, at the Duke Power Company in Charlotte, N.C. to discuss the physics areas outlined on the attached agenda.

The following items were discussed:

1) The Staf f was concerned about the large differences between calculated

.and measured stuck control rod assembly reactivity worths as reported in the Oconee 1 Startup Report.

These differences are attributed to the use of the rod drop measurement method which has an associated large experimental error. Duke stated that their objective in both ejected and stuck rod reactivity worth measurements was to obtain a conservative maximum value for use in their rod ejection analysis and in determining available shutdown margin. The Staff informed Duke that they would prefer a direct comparison of measured vs calculated rod worths in order to assign an uncertainty to calculations. B&W informed the Staf f that better agreement between calculated and measured rod worths has been observed by using a rew neutron resonance model for the Ag-In-Cd rods and calculated control rod group reactivity worths are within 10% of measured worths.

2) Calculated values of the temperature coefficient of reactivity at zero power for various boron concentrations are significantly more positive (conservative) than measured values. However, at various power levels, the trend appears to be reversed. The acceptance criterion, for the measured power Doppler coefficient was that the 4

coef ficient must be more nenative than 0.6 x 10 Ak/k/% FP. All measured 4

~4 Ak/k/% FP and -1.2 x 10 Ak/k/% FP coefficients were between -1.0 x 10 4

4 compared to predicted values ranging from -0.8 x 10 to -0.9 x 10 Ak/k/% FP.

3) Thc incore analysis program used at Oconee to obtain core power distributions from the incore detector readings was discussed at length. The process computer can supply a new power map every six minutes. The surface fit used to compute the power over the entire core by,cxtrapolation of the 52 detector readings works well for small power distribution anomalies. For larger perurbations such as a dropped rod, the fit is not as good but has been observed to be overly conser-vative.

If the computer is out of service, any divergence such as tilt or imbalance can be viaun11y observed immediately; quantitative power distribution evaluat;;ns can be performed by hand within 1-2 hours.

At present, 4 detectors are locked out at Oconee 1 due to bad signals.

The Staff advised Duke and B&W that all vendors would be requested ietailing their incore analysis programs to submit formal ren-t v-6 months.

probably within the o 4)' Operational experience w n Oconee 1 has, in general,not produced any unexpected anomalies. Mc e recent comparisons of allowable boron concentration versus core lifetime were presented and are attached to this report.

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o AGENDA FOR MEETI"G HITH DUKE PO','ER CO.

CHARLOTTE, D.C. - AUG. 13, 1974 1.

Oconee 1 Startup Report Discussion of differences between calculated and mea a.

worths, Discussion of differences between calculated and measured tempera b.

ture coefficients.

Discussion of xenon tests:

c.

1.

Detailed results 2.

Comparison with predictions Why was axial component of diogonal osciliation predicted 3.

to be divergent whereas the induccJ. axial oscillation was not?

Implications of separability in diagonal test - any evidence 4.

of nonseparability?

2.

Incore Analysis Program Extrapolation from detector reading to power distribution a.

Anomalies such as dropped rods and azimuthal xenon tilt.

b.

Failure history of incore detectors

'c.

Input data for program - updated through cycle?

d.

0'perational Experience With Oconee 1 3.

Power distributions vs. calculated f

a.

Boron concentration vs. calculated b.

Rod positions vs. calculated c.

4.

AEC Attendees:

Larry Kopp D. Fieno Marv. Dunenfeld i

I 1

Rod Satterfield

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4

ATTENDANCE' LIST AUGUST 13, 1974 MEETitlo POWER BUILDING - CHARLOTTE, N. C.

Organization Name Duke Power, Steam Production D. C. Ilolt B&W, Nuclear Service Jake Paulson J. F. Harrison B&W, Licensing R. V. Straub B&W, Project Management S. P. Hellman B&W, Project Management B&W, Project Management C. A. Creacy Duke Power, Oconee T. S. Barr Duke Power, Oconee R. L. Wilson Duke Power, Steam Production R. O. Sharpe Duke Power, Steam Production P. M. Abraham Duke Power, Steam Production M. S. Tuckman Duke Power, Steam Production John Kortheuer R. M. Satterfield AEC-L AEC-L M. Dunenfeld AEC-L L. Kopp AEC-L Daniel Fieno Duke Power, Steam Production K. S. Canady B&W, Core Engineering W. T. Brunson Jerry D. Robertson B&W, Fuel Engineering B&W, Fuel Engineering J.,B. Andrews B&W, Core Engineering John R. Coiner Duke Power, Steam Production T. L. Cotton Duke Power, Design Engineering Albert M. Mitry

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