ML19345D849

LER 80-011/03L-0:on 801118,axial Flux Difference Deviated from Target Band.Caused by Improper Interpretation of Tech Specs Resulting in Failure to Lower High Neutron Flux Setpoint.Instruction Clarified

ML19345D849
Person / Time
Site:	Point Beach
Issue date:	12/11/1980
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19345D837	List: ML19345D836 ML19345D849
References
LER-80-011-03L-01, LER-80-11-3L-1, NUDOCS 8012170604
Download: ML19345D849 (3)

Text

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> 8 60 6' OOCK ET NUMBE R ha 69 Eir ENT DATE 74 75 REPORT DATE fl0 EVENT DESCRIPTION AND PROBA8LE CONSEQUENCES h 10121 l During a normal startup, the indicated axial flux dif%rence was noted 1 t o 131 l as deviating from its target band. After unsuccessfully attempting to l 1014 l l return the axial flux difference to the target band within the .:ime I t o lsl l allotted, the reactor was limited to 50% power. However, the high I l o is i I neutron flux setpoint was not reduced to 55% as indicated by Technical l l0l71l Specification 15.3.10.B.2.d.l. This event is reportable in accordance I g o is i ; with Technical Specification 15.6.9.2.B.l. I 7 9 9 80 SYSTEM CAUSE CAUSE COMP. yALyg CODE CODE SUSCODE COMPONENT CODE SUSCODE SUSCODE 10191 7 8 l z I z 16 L^J@ LA_J O I z I z I z I z I z I z l@ LZJ@ LzJ 9 10 tt 12 13 18 19 20 SE QUE NTI AL OCCURRENCE REPORT REveSsON LEn Ro EVENT YE AR REPOR T NO. CODE TYPE NO.

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3J 34 35 36 3d 40 el 42 43 47 CAUSE DESCRIPTION AND COA.RECTIVE ACTIONS h l i l o l I Improper interpretation of Technical Specification 15. 3.10.B.2.d.1 l li t i j l resulted in the failure to lower the high neutron flux setpoint. I g l Supervisory personnel have been made aware of the proper interpretationI g ,13 l l of Technical Specification 15. 3.10.B.2 as it applies to startup 1

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ATTAC.iMENT TO LICENSEE EVENT REPORT NO. 80-Oll/03L-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 2 Docke t No . 50-301 During a normal startup following an outage to repair a safety injection pump, the indicated axial flux difference was noted as deviating from its target band.

After unsuccessfully attempting to return the axial flux to within the target band within the time allotted, the reactor was limited to 50% power as required in Technical Specification 15.3.10.B.2.e. However, the reduction of the high neutron flux setpoint as indicated in Technical Specification 15.3.10.B.2.d.1 to no greater than 55,% was not performed. Administrative controls were employed to ensure reactor power was maintained below 50%. The indicated axial flux was within the target band at 0621 hours0.00719 days <br />0.173 hours <br />0.00103 weeks <br />2.362905e-4 months <br /> on November 19, 1980, and reactor power was increased as allowed by Technical Specifications above 50% at 0435 hours0.00503 days <br />0.121 hours <br />7.19246e-4 weeks <br />1.655175e-4 months <br /> on November 20, 1980.

Upon the expiration of the allotted time to return the axial flux to the target band, the Duty Shif t Supervisor contacted the Duty & Call Superintendent and in the ensuing discussion they decided that the provisions of Technical Specification 15. 3.10.B. 2.d did not apply. Technical Specification 15.3.10.B.2.d refers to a power level "no greater than 90 percent of rated power" and the paragraph following is dencriptive of a reduction in power from 90%

due to exceeding the delta flux limits at an appreciatle power level. The Duty Shift Supervisor and Duty & Call Superintendent resolved the resetting of the power range setpoint was not applicable to the condition of a normal startup sequence. Technical Specification 15.3.10.2.e, "at a power level no greater than 50% of rated power", was the paragraph interpreted as applicable and power was administratively controlled to levels less than 50% until the flux was reestablished in the target band for the period required by che Technical Specifications. The Superintendent -

Technical Services conducted a technical review of the event upon his return on November 21, 1980, with several of the Manager's Supervisory Staff members and the NRC resident inspectors. At this meeting it was determined that the Technical Specifications had been improperly interpreted and that the high neutron flux setpoint should have been lowered to less than or equal to 55% of rated power. All other reactor protection and safety devices were operable and the functional requirement of the high neutron flux setpoint was not comp romised. A revision is being incorporated into Reactor Engineering Instruction, REI 12.0,

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" Technical Specifications and Delta Flux", to incorporate 1

this interpretation of Technical Specifications.

i This item is reportable in accordance with Technical Specification 15.6.9.2.B.l.

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