05000259/LER-1981-014-03, /03L-0:on 810424,MSIVs 1-14,1-15,1-37,1-38,1-51 & 1-52 Exceeded Tech Specs Allowable Leak Rate During Testing.Caused by Slight Steam Erosion Due to Deterioration of Valve Seating Surfaces.Maint & Retest Performed

/03L-0:on 810424,MSIVs 1-14,1-15,1-37,1-38,1-51 & 1-52 Exceeded Tech Specs Allowable Leak Rate During Testing.Caused by Slight Steam Erosion Due to Deterioration of Valve Seating Surfaces.Maint & Retest Performed

ML20004B100
Person / Time
Site:	Browns Ferry
Issue date:	05/20/1981
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20004B098	List: 05000259/LER-1981-014, Forwards LER 81-014/03L-0 05000259/LER-1981-014-03, /03L-0:on 810424,MSIVs 1-14,1-15,1-37,1-38,1-51 & 1-52 Exceeded Tech Specs Allowable Leak Rate During Testing.Caused by Slight Steam Erosion Due to Deterioration of Valve Seating Surfaces.Maint & Retest Performed
References
LER-81-014-03L, LER-81-14-3L, NUDOCS 8105270240
Download: ML20004B100 (2)

LER-1981-014, /03L-0:on 810424,MSIVs 1-14,1-15,1-37,1-38,1-51 & 1-52 Exceeded Tech Specs Allowable Leak Rate During Testing.Caused by Slight Steam Erosion Due to Deterioration of Valve Seating Surfaces.Maint & Retest Performed

Event date:
Report date:
2591981014R03 - NRC Website

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3 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h it was discovered that MSIV's 1-14, l o l 2 l l During refueling outage, while testing MSIV's, g 1-15,1-26,1-27,1-37,1-38,1-51, and 1-52 exceeded the allowable leak rate of g

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Tennessee Valley Authority Form BF-17 Browns Ferry Nuclear Plant BF 15.2 a/24/81 LER SUPPLEMENTAL INFORMATION BFRO 259 / 81014 Technical Specification Involved 4.7.2.1 Reported Under Technical ~ Specification 6.7.2.b(4)

Date of Occurrence 4/24/81 Time of Occurrence 1430 Unit 1

Identification and Description of Occurrence:

Main steam isolation valve leak rate (in standard cubi. feet per hour) is as follows:

1-14, 333.8026 (at 5 psig); 1-15, 3268.". 7 (at 16 psig);

l-26/27, 18.0526; 1-37, 45.6465; l-38, 43.6237; l-51, 2839.9681 (at 5.5 psig); 1-52, 483.9549.

Conditions Prior to Occurrence:

Unit 1 refueling outage Unit 2 at 97%

Unit 3 at 89%

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

Maintenance to be effected and retest to be conducted in accordance with SI 4.7.2.g-3 to verify leakage does not exceed 11.5 SCHI per valve.

Apparent Cause of Occurrence.

Slight steam erosion during power operation.

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

Effect maintenance and retest until leak rate is acceptaole.

Failure Data:

BFRO-50-259/77023, 78034, 8003; 260/74012W, 79007, 80042; 296/78025, 79014, Mlc$Ston: Yeriod - Lifetime; Responsibility - Document Control Supervisor

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