ML19207B316

LER 79-022/03L-0 on 790723:linear Heat Generation Rate Found to Be 0.29 Kw/Ft Above Limit During Daily Core Parameter Check After Reaching 99% Power.Caused by Faulty Computer Reading.After Evaluation 1-3% Power Derate Imposed

ML19207B316
Person / Time
Site:	Brunswick
Issue date:	08/21/1979
From:	Tollison A CAROLINA POWER & LIGHT CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19207B317	List: ML19207B316
References
LER-79-022-03L-01, LER-79-22-3L-1, NUDOCS 7908240406
Download: ML19207B316 (2)

Text

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LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l l (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI 1 6 lo lil8 9l Nl Cl Bl El Pl 1l@l 0l 0l -l 0 0l0l0l0l-l0l0 @l4l1l11il1l@l 7 UCENSEE CODE 14 15 LICENSE NUMBER 25 26 LICENSE TYPE JO l

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REPORT DATE 80 NUMBER EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l Af ter reaching 997, power from a power assention ramp. the daily core parameter check I o a I (PT 1.11) was performed. Linear Heat Generation Rate waa found to be 13.69 kw/ft I o 4 I while the limit is 13.40 kw/f t. Power was immediate1v reduced to 96*/. and PT 1.11 was l l o I s l I again performed. All values were in specification. l o e l Technical Specifications 3.2.4, 6.9.1.9b I o 7 l

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27 l0 l3 l lL l l_l 0l 28 23 30 31 32 TAK N A T ON ONP NT M HOURS 22 S B i ED FOR B. SUPPLIER MANUFAC RER l33X lgl34G l@ l35 B lg l36Z@ l0l1l2l0 37 lY g 41 lNlg N [g l Z l 9 [9 l 9 [g 40 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h g l After technical discussions with the fuel vendor, it was determined that the actual l li li l LHCR was less than read on the process computer since the limiting bundle was on l l 8 X 8R bundle of 150 inch active fuel length, whereasthe process computer conserva-i 3 l tively takes credit for only 144 inch active fuel length. It could not be dei: ermined l i l by the vendor from the information available what the actual LHGR was. (CON'T) [

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LER CONTINUATION - RO# 1-79-022 Facility: BSEP Unit No.1 Event Date: 7-23-79 The nuclear engineer had checked the core paraz ters approximately five (5) hours earlier at 96% power and at the 100% rod pattern. Based on the core parameters at this point, and the projected core performance data supplied by the vendor, he recmanended increasing reactor power to 100% by. incremental flow increases. At 99% power another check of core parameters showed the LHGR ex-ceeding 13.4 kw/ft and power was reduced. Alternate rod patterns were e111uated and it was determined that a 1-3% power derate would be imposed until the fuel burnup and/or an alternate rod pattern will allow full power operation. All nuclear engineers will review this LER to achieve the maximum benefit from this experience.

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