05000296/LER-1982-048-03, /03L-0:on 821011,following Rod Pattern Adjustment, Calculated R Factor Found Less than R Factor Used to Set Average Power Range Monitor Scram & Rod Block.Caused by Insertion of Pattern Revised Rods

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/03L-0:on 821011,following Rod Pattern Adjustment, Calculated R Factor Found Less than R Factor Used to Set Average Power Range Monitor Scram & Rod Block.Caused by Insertion of Pattern Revised Rods
ML20028A548
Person / Time
Site: Browns Ferry 
Issue date: 11/09/1982
From: Nave E
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20028A545 List:
References
LER-82-048-03L-02, LER-82-48-3L-2, NUDOCS 8211220279
Download: ML20028A548 (2)


LER-1982-048, /03L-0:on 821011,following Rod Pattern Adjustment, Calculated R Factor Found Less than R Factor Used to Set Average Power Range Monitor Scram & Rod Block.Caused by Insertion of Pattern Revised Rods
Event date:
Report date:
2961982048R03 - NRC Website

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EVENT DESCalPTIOrJ A JO PMOUAG E C tJ NCES

]l Following a rod pattern adjustment, the calculated "R" factor (RRP/CMFLPD) (0.982) l g I was less than the "R" f actor used to set the APRM scram and rod block (1.0') for g

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Bl 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 15 minutes (T.S. 2.1.A.1.b & d).

There was no effect on public health gl or safety. The calculated scram value was not exceeded during this time.

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Action was taken to revise the control rod pattern.

I gl "R" was within limits in 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and - 15 minutes. Tech specs have been submitted l

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.6 Tennessee Vallev Authority Form BF 17 Brov:ns Ferry Nuclear I'lant BF 15.2 2/12/82 LER SUPPLIGIENTAL INFORMATION BFit0-50 _296_/. 82048 Technical specification Involve (l 2.1.A.L b&d i

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Unit 1 was operating at 97-percent power; unit 2 was in a refueling outage.

These units were unaffected by this event. Unit 3 was operating at 85-percent power following a control rod pattern adjustment. The unit was prevented from returning to full power following the control rod pattern due to feed pump problems. The delay at low flow caused a gradual load line increase as xenon burned out.

h' hen control rods were inserted as required to reduce the load line, "R" was reduced to 0.982 at 0122. This condition was in violation of Technical Specification 2.1.A.1.b and 2.1.A.1.d since the "R" factor setpoint was 1.0.

The red pattern was readjusted and the "R" was within limits (1.008) at 0337. There was no effect on public health or safety. The calculated APRM scram value was i

not exceeded during this event. A technical specification revision ~has been proposed and submitted to the NRC to allow up to six hours for "R" factor being less than the "R" setpoint as currently permitted by unit 1 technical specifications.

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