05000296/LER-1982-038-03, /03L-0:on 820822,calculated R Factor Was Less than R Factor Used to Set Average Power Range Monitor Scram & Rod Block (1.0) for 2-h & 46 Minutes.Caused by Control Rod Pattern Adjustment in Nonequilibrium Xenon Conditions

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/03L-0:on 820822,calculated R Factor Was Less than R Factor Used to Set Average Power Range Monitor Scram & Rod Block (1.0) for 2-h & 46 Minutes.Caused by Control Rod Pattern Adjustment in Nonequilibrium Xenon Conditions
ML20027B906
Person / Time
Site: Browns Ferry Tennessee Valley Authority icon.png
Issue date: 09/21/1982
From: Nave E
TENNESSEE VALLEY AUTHORITY
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20027B903 List:
References
LER-82-038-03L-02, LER-82-38-3L-2, NUDOCS 8209300299
Download: ML20027B906 (2)


LER-1982-038, /03L-0:on 820822,calculated R Factor Was Less than R Factor Used to Set Average Power Range Monitor Scram & Rod Block (1.0) for 2-h & 46 Minutes.Caused by Control Rod Pattern Adjustment in Nonequilibrium Xenon Conditions
Event date:
Report date:
2961982038R03 - NRC Website

text

' NRC FOikM '366' O.S. NUCLEAR RECULATORY COMTAISSION U.77)

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60 61 OOCKET NUMBER 68 69 EVENT DATE 74 75 BEPORT DATE 80-EVENT DESCRIPTION AND PRODABLE CONSEQUENCES h l a l 21 I Followine a maior rod pattern adiustment, the calculated "R" factor-(FRP/CMFLPD) l IO Ia l l (0.957) was less than the "R" factor used to set the APRM scram at5 rod block (1.0)

- I 10141 l for 2 hoters and 46 minutes (T.S. 2.1.A.1 b F &.There was no effect on public health I 2

loisl l or safetv.

The calculated APRM scram value was not exceeded during this time.

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40 di 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i 101 l Event was due to a control rod pattern adiustment in non-equilibrium xenon conditions.1 l i 111 l Pattern adjustment followed a recent startup.

Action was taken to adiust rod pattern.l I i i 21 l "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 46 minutes. Tech specs have been submitted l

11131 I for units 2 and 3 (similar to prhsent unit I tech specs) to allow 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> to l

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  • E.

Earl Nave

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.eYennessee Valley Authority?

Form BF 17 Browns Ferry Nuclear Plant BF 15.2 2/17/82 LER SUPPLEMENTAL INFORMATION

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BFRO 296 / 82038 Technical Specification Involved 2.1.A.1.b & d Reported Under Technical Specification 6.7.2.b.(2h Date Due NRC 09/22/82 1

Event Narrative:

Unit 1 was operating.at 92-percent power; unit 2 was in a refueling outage.

These units were unaffected by this event. Unit 3 was operating at 75-percent power following a major control rod pattern adjustment. The nuclear engineer, i'

through normal core monitoring methods, determined the fraction of rated power j

(FRP) to be less than the core maximum fraction limiting power density (CMFLPD) at 0051. This condition was in violation of Technical Specification 2.1.A.1.b and 2.1.A.1.d since the "R" factor (FRP/CMFLPD) setpoint was 1.0.

Following an OD-1 LPRM calibration to confirm the core parameters, at 0305 power rods were withdrawn to increase the FRP and shaping rods were inserted to decrease CMFLPD. This action brought "R" factor above the "R" factor setpoint at 0337. There was no effect on public health or safety as the calculated APPJ4 scram valve was not exceeded during the event.

A technical specification revision has been previously proposed and submitted to the NRC to allow up to six hours for "R" factor being less than the "R" setpoint, as urrently permitted on unit 1.

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  • Previous Similar Events:

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BFRO-50-259/82019 L.

260/81037, 82022

_, -2C6/81045, 81041, 81040 I

Retention:

period - Lifetime; Responsibility - Document Control Supervisor

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