05000259/LER-1980-028-03, /03L-0:on 800403,while Performing Procedure RTI-5 & After Exceeding 40% Power,Discovered That Reactor Pressure During Scram Timing Tests Had Been 950 Psia Rather than Required 950 Psig.Caused by Personnel Error

/03L-0:on 800403,while Performing Procedure RTI-5 & After Exceeding 40% Power,Discovered That Reactor Pressure During Scram Timing Tests Had Been 950 Psia Rather than Required 950 Psig.Caused by Personnel Error

ML19309G751
Person / Time
Site:	Browns Ferry
Issue date:	05/01/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19309G749	List: 05000259/LER-1980-028, Forwards LER 80-028/03L-0 05000259/LER-1980-028-03, /03L-0:on 800403,while Performing Procedure RTI-5 & After Exceeding 40% Power,Discovered That Reactor Pressure During Scram Timing Tests Had Been 950 Psia Rather than Required 950 Psig.Caused by Personnel Error
References
LER-80-028-03L, LER-80-28-3L, NUDOCS 8005070498
Download: ML19309G751 (2)

LER-1980-028, /03L-0:on 800403,while Performing Procedure RTI-5 & After Exceeding 40% Power,Discovered That Reactor Pressure During Scram Timing Tests Had Been 950 Psia Rather than Required 950 Psig.Caused by Personnel Error

Event date:
Report date:
2591980028R03 - NRC Website

text

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EvtNT DATE 74 7'a REPORT OATE 80 cvE*.T cr$CmPTION AND PRC9ABLE CONSEGUENCES During data reduction of scram tim g data taken while performing procedure RTI-5, and af ter exceeding 407 power, it was discovered that the reactor pressure during g

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' Tennessee Valley Authority Form BF-17 Browns Ferry Nuclear Plant BF 15.2 1/10/79 LF.R SUPPLEMENT AL INFORMATION BFRO-50 259 / 8028 T_rhnical Spe~ificaticn Involved 4.3.C.1 lleported Under Technical Specification 6.7. 2.b (3) r Date of Occurrence 4/3/80 Time of Occurrence 1300 Unit 1

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Identification antj, Description of Occupence: During data reduction of scram timing test. Data, taken while performing procedure RTI-5, and after exceeding 407. power it was discovered that the reactor pressure during scram timing tssts had been 950 PSIA rather than the required 950 PSIG.

Conditions Prior to Occurrence:

Unit 1 - @-547.

Unit 2 - @~1007.

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Unit 3 - @~1007.

Action specified in the Technical Specification Surveillance Requirements met due to inoperable equipment. Describe.

NA Apparent Cause af Occurrence: Personnel coordinating scram testing failed to assure that tTie prerequisitFlor reactor pressure was met.

This led to exceeding

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407. PWR without valid scram test data.

Analysis cf Occurren...

There was no danger to plant equipment. There was no activity rsRase, no'~psrsonnel exposure or injury and no danger to health or safety of the public.

Corrective Action

Reduced load and re-performed scram timing test Failure Data:

NA

• Retention :

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision :

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