05000296/LER-1981-041-03, /03L-0:on 810822,during Startup After Tying Turbine Generator Online,First Process Computer P-1 Was Run. Frp/Cmflpd (R) Calculated to Be Less than Tech Spec Setpoint.Caused by Reactor Starting Up

/03L-0:on 810822,during Startup After Tying Turbine Generator Online,First Process Computer P-1 Was Run. Frp/Cmflpd (R) Calculated to Be Less than Tech Spec Setpoint.Caused by Reactor Starting Up

ML20010G848
Person / Time
Site:	Browns Ferry
Issue date:	09/15/1981
From:	Holder G TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20010G836	List: 05000296/LER-1981-041, Forwards LER 81-041/03L-0 05000296/LER-1981-041-03, /03L-0:on 810822,during Startup After Tying Turbine Generator Online,First Process Computer P-1 Was Run. Frp/Cmflpd (R) Calculated to Be Less than Tech Spec Setpoint.Caused by Reactor Starting Up
References
LER-81-041-03L-02, LER-81-41-3L-2, NUDOCS 8109220585
Download: ML20010G848 (2)

LER-1981-041, /03L-0:on 810822,during Startup After Tying Turbine Generator Online,First Process Computer P-1 Was Run. Frp/Cmflpd (R) Calculated to Be Less than Tech Spec Setpoint.Caused by Reactor Starting Up

Event date:
Report date:
2961981041R03 - NRC Website

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J o 12 l l During startup, af ter tying turbine generator online, first process computer g

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FRP/CMFLPD (R) was calculated to be less than setroint of 0.802.

g j o j.i j l (T.S. 2.1. A) In the course of the startup, R tJas brought within limits. Setting l

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g l of rod pattern reduced the peak to everage power ratio.

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Tennessee Valley Authority Form BF 17 Browns Ferry Nuclear Plant BF 15.2

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1. Kit SUPI't.EMENTAI. INI'ORM ATION i

BFitO-50 296 / 81041 Te chnical Specification involved 2.1.A 1(cported Under Technical Sp, cification _6.7.2.b(2)

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!).ite of Occurrence 8/2'!/81 Time of Occurrence 2047 Unit 3

Identification and l>escrip~ tion of Occurrence:

During staitiip^iftsi ty'ing tuib'ine generaiof online, first process computer

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(P-1) was run. FRP/CMFI.PD (R) was calculated to be less than the R setpoint of 0.802.

Conditions Prior to Occurrence:

Unit 1 in refueling outage.

U:.it 2 at 91%.

Unit 3 at 40%.

Action specified in :he Technical Specification Surveillance Requirements met du? to,i1pperable equipment. Describe.

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None Apparent Cause of Occurrence:

Reactor starting up.

Analysis of Occurrence:

There was no danger to the health or safety of the public, no release of activity, no damage to the plant or equipment, and no resulting significant chain of events.

Corrective Action

During the course of startup, shaping of power was controlled by setting of rod patterns to reduce the peak to average power. STA's have been instructed c.o set R setpoint more conservatively during startup.

Failure Data: BFRO-50-260/81037, 81018; 296/81040 Hetention:

Per' d - 1.ifetime; Responsibility - Document Control Supervisor

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