05000296/LER-1981-018-03, /03L-0:on 810414,core Max Fraction of Limiting Power Density Found Exceeding Tech Spec Limit Following Local Power Range Monitor Calibr.Possibly Caused by Instrument Drift.Monitor Recalibr within Tech Spec Limits

/03L-0:on 810414,core Max Fraction of Limiting Power Density Found Exceeding Tech Spec Limit Following Local Power Range Monitor Calibr.Possibly Caused by Instrument Drift.Monitor Recalibr within Tech Spec Limits

ML19347E633
Person / Time
Site:	Browns Ferry
Issue date:	05/08/1981
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19347E631	List: 05000296/LER-1981-018, Forwards LER 81-018/03L-0 05000296/LER-1981-018-03, /03L-0:on 810414,core Max Fraction of Limiting Power Density Found Exceeding Tech Spec Limit Following Local Power Range Monitor Calibr.Possibly Caused by Instrument Drift.Monitor Recalibr within Tech Spec Limits
References
LER-81-018-03L, LER-81-18-3L, NUDOCS 8105130157
Download: ML19347E633 (2)

LER-1981-018, /03L-0:on 810414,core Max Fraction of Limiting Power Density Found Exceeding Tech Spec Limit Following Local Power Range Monitor Calibr.Possibly Caused by Instrument Drift.Monitor Recalibr within Tech Spec Limits

Event date:
Report date:
2961981018R03 - NRC Website

text

NRC FOIM 364 U. S. NUCLEAR REGULATORY COMMISSION

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8 60 61 QoCKET NUM8ER 68 69 EVENT D ATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PRCSA8LE CONSEQUENCES h l o l a i,1 During normal operation, following completion of a local power range monitor l

I o l a i I calibration, the core maximum fraction of limiting power density was calculated to be l Io I4! I 1.003 which exceeds the limit of < l.000 prescribed by T.S. 3.5.J.

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loIsi,1 effects on the health or safety of the public. There were no redundant systems.

l [oIei'l Previous similar events: BFRO-50-260/81005, 81006.

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33 34 35 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h l i l o l l Calibration of the LPRM's via OD-1 revealed a CMFLPD of 1.003.

Possible LPRM drift j i i l i i I just prior to or during LPRM calibration. Calibration was performed within the I

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Form BF-17 Browns Ferc'y Nuclear Plant BF 15.2 5/24/81 LER SUPPLEMENTAL INFORMATION BFRO 296 / 81018 Technical Specification Involved 3.5.J Reported Under Technical Specification 6.7.2.b (2)

Date of Occurrence 4/14/81 Time of Occurrence 1447 Unit 3

Identification and Description of Occurrence:

Following completion of an OD-1, the core maximum fraction of limiting power density (CMFLPD) was calculated by the process computer program P-1 to be

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1.003.

CMFLPD is limited to f.,1.000 by T.S. 2.1.A.

Conditions Prior to occurrence:

Unit 1 at refueling outage.

I Unit 2 at 99%.

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Unit 3 at b4 Action specified in the Technical Specification Surveillance Requirements met due to inocerable ecuipment.

Describe.

Recirculation flow was decreased initially, and then control rods were inserted to reduce CMFLPD.to under 1.000.

The 1514 P-1 calculated CMFLPD to be 0.979.

Accarent Cause of Occurrence:

Possible LPRM drif t just prior to or during LPRM calibration.

Analysis of Occurrence:

There was no damage to plant or equipment. There was no activity release, no personnel exposure or injury and no danger to the health or safety of the.mihlic.

Corrective Action

Recirculation flow was decreased and control rods inserted to reduce CMFLPD for short term corrective action. No further recurrence control required.

Failure Data:

BFRO-50-260/81005, 81006.

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• Retention:

Period - Lifetime; Respersibility - Document Control Supervisor

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• Revision:

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