ML19209A310

LER 79-083/01T-0:on 790917,at 5:20 PM in Mode 1,reactor Power Level of 96% Exceeded Power Level Cutoff Limit of 92%. Caused by Personnel Error.Procedures Revised to Prevent Reoccurrence

ML19209A310
Person / Time
Site:	Crystal River
Issue date:	09/24/1979
From:	Cooper J FLORIDA POWER CORP.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19209A303	List: ML19209A302 ML19209A310
References
LER-79-083-01T, LER-79-83-1T, NUDOCS 7910030503
Download: ML19209A310 (2)

Text

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(SEE ATTACHED SUPPLEMENTARY IN70RMATIONi S.:. RET)

SUPPLEMENTARY INFORMATION Report No.: 50-302/79-083/0lT-0 Facility: Crystal River Unit #3 Report Date: 24 September 1979 Occurrence Date: 17 September 1979 Identification of Occurrence: Failure to comply with the most conservative action statement of a limiting condition for operation reportable under Technical Specification 6.9.1.8.b. Failure of a component which could have prevented che fulfillment of the functional requirements of a system used to cope with accidents analyzed in the FSAR, reportable under Technical Specification 6.9.1.8.e. Conditions Prior to Occurrence: Mode 1 power operation (96%). Description of Occurrence: At 1720 following the recalibration of "B" feedwater loop flow transmitter SP-8B-DPT2, and the completion of Heat Balance Calculation SP-312, it was deter-mined that Reactor power exceeded the power level cutoff limit of 92% specified by Technical Specification 3.1.3.8. Reactor power derived from heat balance cal-culations was 96% versus an indicated Reactor power of 86%, with Xenon reactivity within 19% of equilibrium value for rated thermal power. Reactor power was stabilized at 96%. A group 21 tilt / imbalance / insertion limit program was per-for=ed to evaluate core conditions. All parameters were within specification. Power range nuclear instrumentation was recalibrated to 96%. Upon completion of the NI calibration, Reactor power was reduced to less than 92% at 1824. Designation of Apparent Cause: The cause of this event is attributed to failed "B" feedwater loop flen trans-mitter SP-8B-DPT2. Reactor power was stabilized at 96% to recelibrate power range nuclear instrumentation to comply with the action statement requirements of Technical Specificceton 3.3.1.1. This decision was made in lieu of the more conservative requiremente of Technical Specification 3.1.3.8, based on th, satis-factory results obtained from the group 21 tilt / imbalance / insertion limit program. Corrective Action: A revision to the Plant Power Operation Procedure, OP-204 is being implement 2d to assure that power range nuclear instrumentation is in agreement with heat balance calculations at 72% 85%, and at 100% power. A revision to Power Range Nuclear Instrumentation Calibration Procedure SP-ll3 is also being implemented to allow for a calibration check of the feedwater flow transmitters prior to performing heat balance calculations. In addition, a review of this event was conducted by the Operations Superintendent for supervisory Operations personnel to identify the concerns regarding "most conservative" aspects in conflicting action state-ment situations. Failure Data: This is the first reported occurrence of an event of this type.

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