05000260/LER-1979-007-03, /03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested

/03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested

ML18024A816
Person / Time
Site:	Browns Ferry
Issue date:	05/29/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024A815	List: 05000260/LER-1979-007, Forwards LER 79-007/03L-0 05000260/LER-1979-007-03, /03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested
References
LER-79-007-03L-01, LER-79-7-3L-1, NUDOCS 7905310369
Download: ML18024A816 (2)

LER-1979-007, /03L-0 on 790503:during Refueling Outage,Five MSIVs Exceeded Leakage Limits.Caused by Irregularities on Valve Seating Surfaces & Entrapment of Debris Under Seating Surfaces.Valves Will Be Repaired & Retested

Event date:
Report date:
2601979007R03 - NRC Website

text

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60 61 DOCKET NUMBER 68 69 EVENT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES 010 Durin a refuelin outa e

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4. 7.A. 2. i.

Leakage rates were:

FCV 1-15:

1847 SCFH; FCV 1-26:

455 SCFH; FCV 1-52:

343 SCFH'CV 1-14:

206 SCFH; FCV 1-51 25 SCFH.

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Redundant systems were not applicable since the reactor was in the refueling mode.

There was no hazard to the public health or safet

. Previous occurrence:

BFRO-50-260/

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789.

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The defective valves were 26 inch Atwood-Morill lobe valves, neumatic actuation, o crating pressure rated 1250 psig at 575 P.

The cause of the occurrence was irre ulari-ties on the valve seating surfaces and entrapment of debris under seating surfaces. The 3

valves wil1 be repaired and retested.

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Form BF-17 BF 15.2 6/09/78 LER SUPPLEMENTAL INFORMATION BFRO 260 /

797 'echnical Specification Involved 4.7.A.2.i Reported Under Technical Specification 6.7.2.b.2 Date of Occurrence 5/3/79 Tme of Occurrence 1400

/

Identification and Descri tion of Occurrenc'e:

Unit 2

Five MSIV's exceeded the leak rate allowed by T.

S. 4.7.A.2.i during local leak rate testing.

Leakage rates were:

FCV 1-15:

1847 SCFH; FCV 1-26:

455 SCFH; FCV 1-52:

343 SCFH; FCV 1-14:

206 SCFH; FCV 1-51:

25 SCFH.

Conditions Prior to Occurrence:

Unit shutdown for refueling.

The reactor head was removed.

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

Describe.

Repair and retest.

A arent Cause of Occurrence:

Degradation of valve seating surfaces due <o normal wear and entrapment of debris under seating. surfaces.

Anal sis of Occurrence:

Thete was no hazard to the public health or safety.'orrective Action:

Valves will be repaired and satisfactorily tested prior to returning'the unit to service.

Failure Data:

BFRO-50-260/789.

Tennessee Valley Authority - Browne Ferry Nuclear Plant 4