05000260/LER-1980-042-03, LER:80-042/03L-0:on 800929,during Leak Rate Testing on Main Steam Isolation Valves,Valves 1-14,1-15,1-26 & 1-52 Exceeded Allowable Leakage Rate.Caused by Seating Surface Deterioration.Valves Repaired & Retested

LER:80-042/03L-0:on 800929,during Leak Rate Testing on Main Steam Isolation Valves,Valves 1-14,1-15,1-26 & 1-52 Exceeded Allowable Leakage Rate.Caused by Seating Surface Deterioration.Valves Repaired & Retested

ML18025B169
Person / Time
Site:	Browns Ferry
Issue date:	10/27/1980
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18025B167	List: 05000260/LER-1980-042, Forwards LER 80-042/03L-0 05000260/LER-1980-042-03, LER:80-042/03L-0:on 800929,during Leak Rate Testing on Main Steam Isolation Valves,Valves 1-14,1-15,1-26 & 1-52 Exceeded Allowable Leakage Rate.Caused by Seating Surface Deterioration.Valves Repaired & Retested
References
LER-80-042-03L-02, LER-80-42-3L-2, NUDOCS 8011040484
Download: ML18025B169 (4)

LER-1980-042, LER:80-042/03L-0:on 800929,during Leak Rate Testing on Main Steam Isolation Valves,Valves 1-14,1-15,1-26 & 1-52 Exceeded Allowable Leakage Rate.Caused by Seating Surface Deterioration.Valves Repaired & Retested

Event date:
Report date:
2601980042R03 - NRC Website

text

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60 61 DOCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT DESCRIPTION AND PROBAOLE CONSEQUENCES Q10

'While in cold shutdown for refueling, local leak rate testin was erformed on main rate of. 11.5 standard cubic feet per hour.

Reference T.S. 3.7.A.

There was no danger to health or safety of public.

No significant resulting events.

Previous occurrence BFRO-50-259/80003

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Os 33 34 35 36 37 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS Q27 Valves exceeded leak rate due to seating surface deterioration caused b

normal wear and steam erosion.

Valves will be re aired and tested er SI 4.7'.A.2. -3.

twood-Morrill, 26" globe, with stellite seats, valve ratin 1250 si at 575 F

980 si normal operating pressure.

Recurrence control bein studied.

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FACILITY STATUS

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as Tennessee Valley Authority Browns Ferry Nuclear Plant Form BF-17 BF 15.2 1/10/79 LER SUPPLEMENTAL INFORMATION s

BFRO 260 /8042 Technical Specification Involved 3 IA Reported Under Technical Specification 6.7.2.a(3)

Identification and Descri tion'of Occurrence:

Hain steam isolation valves 1-14, 1-15, 1-26 and 1-52 exceeded the allowable leak rate of 11.5.SCFH per valve.

Conditions 'Prior to Occurrence:

Unit 1 8 81%

power Unit 2 8 0 refueling outage Unit 3 8 97%

po~er Action specified in the Technical Specification Surveillance Requirements met due to ino erable e ui ment.

Describe.

~A parent Cause of Occurrence:

Valve seat deterioration due to normal wear and steam erosion.

Anal sis of Occurrence:

There was no damage to plant equipment.

There was no activity release, no personnel exposure or injury and no danger to the health or safety of the public.

Corrective Action

HSIV's were repaired and then retested in accordance with SI 4.7.A.2.g-3 until satisfactory results were obtained.

Long-term recurrence control being studied by EN DES.

Failure Data:

BFRO 50 259/77023 a 259/78034 s 260/79007 a 296/78025 296/7901 4 a 259/80003

• Retention:

eriod - Lifetime; Responsibility - Administrative Supervisor

• Revision:

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