IR 05000266/1978020

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IE Inspec Rept 50-266/78-20 on 781013-14 During Which No Items of Noncompliance Were Noted.Major Areas Inspected Incl:Measurement of Control Bank Worth by Boron Dilution & of Control & Shutdown Bank Worths
ML20027A526
Person / Time
Site: Point Beach 
Issue date: 11/13/1978
From: Chow E, Kohler J, Streeter J
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
To:
Shared Package
ML20027A525 List:
References
50-266-78-20, NUDOCS 7812140147
Download: ML20027A526 (3)


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U.S. NUCLEAR REGULATORY COMMISSION

0FFICE OF INSPECTION AND ENFORCEMENT

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REGION III

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Report No. 50-266/78-20 f

l Docekt No. 50-266 License No. DPR-24 i

Licensee: Wisconsin Electric Power Company 231 West Michigan i

Milwaukee, WI 53203 i

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Facility Name:

Point Beach Unit 1

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Inspection At:

Point Beach Site, Two Creeks, WI Inspection Conducted:

October 13-14, 1978 i

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J.'(Ibluv Inspectors:

J. E. Kohler It b lb

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E. T. Chow

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i Approved By:

J. F. Streeter, Chief Nuclear Support Section 1

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Inspection Summarv

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r Inspection on October 13-14, 1978 (Report No. 50-266/78-20)

Areas Inspected: Measurement of the reference control bank worth by boron dilution; measurements of control and shutdown bank worths

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by rod swap technique.

The inspection involved 16 inspector-hours

onsite by two NRC inspectors.

Results: Of the areas inspected, no items of noncompliance or deviations were identified.

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f DETAILS 1.

Persons Contacted

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  • G. Reed, Manager, Nuclear Power Division

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  • J.

Zach, Reactor Engineer l

P. Kurtz, Engineer

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  • J.

Greenwood, Assistant to the Manager

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  • denotes those present during the exit interview conducted on

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the telephone on October 16, 1978.

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2.

Control and Shutdown Bank Worth Measurements

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The inspectors witnessed the measurements of contro,' rand shut-down bank worth.

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The first phase of testing was to determine the reactivity of l

Control Bank A, the bank with the higA6st worth. The bank was

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inserted into the reactor core whiIs simultaneously diluting the reactor coolant system to 5Aintain criticality at hot zero

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power (HZP). The reactor esclant was periodically sampled for l

determination of boron cencentration.

The change of reactivity

for each step was calculated by a reactivity computer and

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recorded on a strip chart. The inspectors observed the procedures j

for analyzing the data which involved manual measurement and

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summation of strip chart data by the licensee.

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The recond phase of testing was to utilize the rod swap (bank j

exchange) method with Control Bank A as the reference for evaluation

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of the worths of the other banks. With Control Bank A initially

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inserted into the reactor core, another bank was inserted a few

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steps, and Control Bank A was withdrawn a few steps to maintain i

HZP.

This procedure continued until the bank being measured

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was fully inserted in the core, and the critical height of the l

Control Bank A was recorded.

The same procedure was followed i

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for all other banks.

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3.

Results of Rod Swap Tests i

i The test results showed that the discrepancy between the predicted I

and measured (P/M) worths of Control Bank B was -20.3% which

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was outside the -15% criterion specified in the review criteria.

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In addition, the P/M worth discrepancy of Control Bank A was

+12%, which was larger than the +10% specified in the review

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criteria. However, the discrepancy between the predicted and measured (P/M) sum of the worths of six banks was within +10%

as specified in the acceptance and review criteria established by

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the licensee and fuel vendor.

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In accordance with the provisions of a NRR letter to the licensee dated October 12, 1978, the onsite safety review committee must resolve the Control Bank A and B discrepancies prior to reaching 100% power equilibrium xenon and IE is to be notified of any remedial action deemed necessary.

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Management Exit The management exit was conducted by Mr. J. Kohler on October 16, 1978, by telephone. The inspector stated that the information regarding the test and its results has been relayed to NRR for review. As noted in Paragraph 3, the onsite safety review committee is to resolve the control rod bank discrepancies prior l

to reaching 100% power equilibrium xenon, and IE is to be notified of the remedial action.

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