05000260/LER-1980-004, Forwards LER 80-004/03L-0

Forwards LER 80-004/03L-0

ML18024B357
Person / Time
Site:	Browns Ferry
Issue date:	02/20/1980
From:	Calhoun J TENNESSEE VALLEY AUTHORITY
To:	James O'Reilly NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024B358	List: 05000260/LER-1980-004, Forwards LER 80-004/03L-0 05000260/LER-1980-004-03, /03L-0:on 800122,reactor Water Level Switch LIS-3- 203D Switch 2 Exceeded Tech Spec Limit During Normal Operation.Caused by Model 288A Switch Drifting Above Setpoint.Switch Tested,Inspected & Recalibr
References
NUDOCS 8002260722
Download: ML18024B357 (6)

LER-1980-004, Forwards LER 80-004/03L-0

Event date:
Report date:
2601980004R00 - NRC Website

text

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~ g TENNESSEE VALLEYAUTHORITY CHATTANOOGA. TENNESSEE 37401 716 Edney Building FEB 80 1980 Hr. James P. O~Reilly, Director U.S. Nuclear Regulatory Commission Office of Inspection and Enforcement Region XX.

101 Marietta Street, Suite 3100 Atlanta, Georgia 30303 k"

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Dear Hr. O'Reilly:

TKZINESSEE VALLEY AUTHORXTY BROIlNS FERRY NUCLEAR PLANT UNXT 2 - DOCKET NO. 50"260 FACILITY OPERATXNG LICENSE DPR-52 REPORTABLE OCCURRENCE REPORT BFRO-50-260/8004 The enclosed report provides details concerning reactor water level switch LXS-3-203D switch 2 which exceeded the technical specification limit of equal to or less than 583 inches above vessel zero (Technical Specification table 3.2.B) during normal operation while performing Surveillance Instruction 4,1.A-7, This report is submitted in accordance with Brows Perry'unit 2 Technical Specification 6.7.2.b(2).

Very truly yours, TENNESSEE VALLEY AUTHORITY

'J. R, Calhoun Director of Nuclear Power Enclosure (3) cc (Enclosure):

Director (3) t Office of Management Information and Program Control U.S. Nuclear Regulatory Commission Ifashington, DC 20555 Director (40)

Office of Inspection and Enforcement U S. Nuclear Regulatory Commission Ilashington, DC 20555 Mr. BillLavallee Nuclear Safety Analysis Center Palo Alto, California 94303 Mr. R. P.'ullivan, NRC Inspector, Browns Perry

/<PE i An Equal Opportunity Employer

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Q9 60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 010 Durin normal o eration while erformin SX 4. 1.A-7 reactor water level switch LES-

~o3 3-203D switch 2 exceeded the T.

S. limit of e ual to or less than 583 inches above

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S. table 3.2.B There was no effect on the ublic health or safet

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Redundant switches were o erable.

Previous occurrence:

296/7824, 259/741, 259/7333,

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259 7341 259 7322 and 296 773.

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Q26 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION ANDCORRECTIVE ACTIONS Q27 o

The model 288A had drifted above the set oint.

The switch was ins ected recalibrated functionall tested for re eatabilit and returned to service immediatel rence control action is required., Other unit's switches are checked on a re ular SI schedule.

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FACIUTY STATUS

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10 NAME OF PREPARER 68 69 PHONE:

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e ece Tenn es see Valley Authority Brogans Ferry Nuclear Plant LER SUPPLEitIFNTAI. INFORMATION Form BF-17 HF 15. 2 1/10/79 BFBO 260 /

8004

'I'cchnical Specification Involve> >rted Under Technical Specification 6.7e2 b(2)

Date of Occuvrence 1/22/80 Time of Occuvrence 1500 Unit Identification and Description'of Occurrence:

Reactor water level switch LXS-3-203D switch 2 exceeded the T.

S. limit by

.4 inches of water.

Conditions Prior to Occurrence:

U-1 refueling.

U-2 77%.

U-3 98%.

Action specified in the Technical Specification Suvveillance Requirements mct due to~inc erebie equidtteoot.

Describe.

Repair in 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or declare the system or component inoperable.

Apparent Cause of Occurrence:

Instrument drift.

Analysis of Occurrence:

There was no damage to plant equipment, no activity release, no personnel exposure or in)ury and no danger to health or safety of the public.

Corrective Action

Inspected, recalibrated and functionally tested.

I'ailui e Data:

296/7824, 259/741, 259/7333, 259/7341, 259/7322 and 296/773.

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