ML19329A685: Difference between revisions

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| document report number = RO-287-76-15, NUDOCS 8001090670
| document report number = RO-287-76-15, NUDOCS 8001090670
| package number = ML19329A679
| package number = ML19329A679
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO,LER), TEXT-SAFETY REPORT
| document type = REPORTABLE OCCURRENCE REPORT (SEE ALSO AO LER), TEXT-SAFETY REPORT
| page count = 1
| page count = 1
}}
}}
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Oconee Unit 3 Report No: 50-287/76-15 Report Date: September 27, 1976 Occurrence Date: September 11, 1976 Facility: Oconee Unit 3, Seneca, South Carolina Identification of Occurrence:
Oconee Unit 3
Incorrect " thermal power best" valve resulting from erroneous data input to Core Thermal Power Analysis Program Conditions Prior to Occurrence: Unit at 53% full power Description of Occurrence:
      .
On September 11, 1976, it was discovered that on September 10, 1976, a data val,ue had been incorrectly input into the Core Thermal Power Analysis (CTPA) program on the Oconee Unit 3 computer.
Report No: 50-287/76-15 Report Date: September 27, 1976 Occurrence Date: September 11, 1976 Facility: Oconee Unit 3, Seneca, South Carolina Identification of Occurrence:     Incorrect " thermal power best" valve resulting from erroneous data input to Core Thermal Power Analysis Program
As a result, for approximately 26 hours, the " thermal power best" computer point, a determination of the reactor power calculated from primary and secondary system heat balances, indicated a power level of 44% full power rather than the correct value of 53% full power.
,
Conditions Prior to Occurrence: Unit at 53% full power Description of Occurrence:
On September 11, 1976, it was discovered that on September 10, 1976, a data val,ue had been incorrectly input into the Core Thermal Power Analysis (CTPA) program on the Oconee Unit 3 computer. As a result, for approximately 26 hours, the " thermal power best" computer point, a determination of the reactor power calculated from primary and secondary system heat balances, indicated a power level of 44% full power rather than the correct value of 53% full power.
Upon discovery of this error the computer program was corrected and the power range out of core detectors which had previously been calibrated to the incor-rect reactor power calculation, were recalibrated to the corrected " thermal power best" value.
Upon discovery of this error the computer program was corrected and the power range out of core detectors which had previously been calibrated to the incor-rect reactor power calculation, were recalibrated to the corrected " thermal power best" value.
Apparent Cause of Occurrence:
Apparent Cause of Occurrence:
This incident resulted from the incorrect storage of a data valus within the CTPA program. The technician involved, needing a computer location in which to store a numerical constant, placed the constant in a location occupied by a zero, thinking such to be an unused computer memory location.       The zero stored in that location.however, was normally used by the program for calcu-lation of Reactor Coolant pressure. Therefore, changing this data value resulted in an incorrect pressure calculation and in a 10% error in the " thermal power best" determination.
This incident resulted from the incorrect storage of a data valus within the CTPA program. The technician involved, needing a computer location in which to store a numerical constant, placed the constant in a location occupied by a zero, thinking such to be an unused computer memory location.
The zero stored in that location.however, was normally used by the program for calcu-lation of Reactor Coolant pressure. Therefore, changing this data value resulted in an incorrect pressure calculation and in a 10% error in the " thermal power best" determination.
Analysis of Occurrence:
Analysis of Occurrence:
This incident resulted in the operation of the unit for a period of approxi-mately 26 hours during which the out-of-core detectors were indicating a power level approximately 10% below the actual power. During this time, however, no safety limits were exceeded because the unit was operating at a reduced power level in preparation for a refueling outage. It is concluded therefore, that the health and safety of the public was not affected by this occurrence.
This incident resulted in the operation of the unit for a period of approxi-mately 26 hours during which the out-of-core detectors were indicating a power level approximately 10% below the actual power. During this time, however, no safety limits were exceeded because the unit was operating at a reduced power level in preparation for a refueling outage.
It is concluded therefore, that the health and safety of the public was not affected by this occurrence.
i Corrective Action:
i Corrective Action:
It is felt that this occurrence is an isolated incident.       However, efforts are underway to evaluate the present controls for computer software and to imple-ment, as determined necessary, appropriate formal administrative policies.
It is felt that this occurrence is an isolated incident.
However, efforts are underway to evaluate the present controls for computer software and to imple-ment, as determined necessary, appropriate formal administrative policies.
8001090870
8001090870
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Latest revision as of 07:07, 31 December 2024

RO 287/76-15:on 760911,incorrect Power Level Indication on Thermal Power Best Computer Point.Caused by Incorrect Data Value Storage within Program.Present Software Controls Evaluated & Appropriate Administrative Policies Implemented
ML19329A685
Person / Time
Site: Oconee 
Issue date: 09/27/1976
From:
DUKE POWER CO.
To:
Shared Package
ML19329A679 List:
References
RO-287-76-15, NUDOCS 8001090670
Download: ML19329A685 (1)


Text

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Oconee Unit 3 Report No: 50-287/76-15 Report Date: September 27, 1976 Occurrence Date: September 11, 1976 Facility: Oconee Unit 3, Seneca, South Carolina Identification of Occurrence:

Incorrect " thermal power best" valve resulting from erroneous data input to Core Thermal Power Analysis Program Conditions Prior to Occurrence: Unit at 53% full power Description of Occurrence:

On September 11, 1976, it was discovered that on September 10, 1976, a data val,ue had been incorrectly input into the Core Thermal Power Analysis (CTPA) program on the Oconee Unit 3 computer.

As a result, for approximately 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br />, the " thermal power best" computer point, a determination of the reactor power calculated from primary and secondary system heat balances, indicated a power level of 44% full power rather than the correct value of 53% full power.

Upon discovery of this error the computer program was corrected and the power range out of core detectors which had previously been calibrated to the incor-rect reactor power calculation, were recalibrated to the corrected " thermal power best" value.

Apparent Cause of Occurrence:

This incident resulted from the incorrect storage of a data valus within the CTPA program. The technician involved, needing a computer location in which to store a numerical constant, placed the constant in a location occupied by a zero, thinking such to be an unused computer memory location.

The zero stored in that location.however, was normally used by the program for calcu-lation of Reactor Coolant pressure. Therefore, changing this data value resulted in an incorrect pressure calculation and in a 10% error in the " thermal power best" determination.

Analysis of Occurrence:

This incident resulted in the operation of the unit for a period of approxi-mately 26 hours3.009259e-4 days <br />0.00722 hours <br />4.298942e-5 weeks <br />9.893e-6 months <br /> during which the out-of-core detectors were indicating a power level approximately 10% below the actual power. During this time, however, no safety limits were exceeded because the unit was operating at a reduced power level in preparation for a refueling outage.

It is concluded therefore, that the health and safety of the public was not affected by this occurrence.

i Corrective Action:

It is felt that this occurrence is an isolated incident.

However, efforts are underway to evaluate the present controls for computer software and to imple-ment, as determined necessary, appropriate formal administrative policies.

8001090870

_.