05000296/LER-1979-017-79, /03L-0:on 790917,during Leak Rate Testing,Total Leak Rate Exceeded Tech Spec Limit.Caused by Deterioration of Valve Seats Through Normal Operation on Main Steam & Containment Inerting Sys.Valves Will Be Repaired & Retested

/03L-0:on 790917,during Leak Rate Testing,Total Leak Rate Exceeded Tech Spec Limit.Caused by Deterioration of Valve Seats Through Normal Operation on Main Steam & Containment Inerting Sys.Valves Will Be Repaired & Retested

ML18024B060
Person / Time
Site:	Browns Ferry
Issue date:	10/17/1979
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18024B059	List: 05000296/LER-1979-017, Forwards LER 79-017/03L-0 05000296/LER-1979-017-79, /03L-0:on 790917,during Leak Rate Testing,Total Leak Rate Exceeded Tech Spec Limit.Caused by Deterioration of Valve Seats Through Normal Operation on Main Steam & Containment Inerting Sys.Valves Will Be Repaired & Retested
References
LER-79-017-79-03L, LER-79-17-79-3L, NUDOCS 7910230459
Download: ML18024B060 (5)

LER-1979-017, /03L-0:on 790917,during Leak Rate Testing,Total Leak Rate Exceeded Tech Spec Limit.Caused by Deterioration of Valve Seats Through Normal Operation on Main Steam & Containment Inerting Sys.Valves Will Be Repaired & Retested

Event date:
Report date:
2961979017R79 - NRC Website

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~ technical specification 4.7.A.2.g.

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~allowable 60 percent L~per 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or 655.9 SCFH.

There were no significant result-l

~ing events nor any danger to health or safety of the public.

[occurrence was reported on BFRO-50/260-7914..

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Tennessee Valley Authority I3rowns Ferry Nuclear Plant Form BF-17 B".15.2 I/10/79 LER SUPPLEMI'.N'I'AL INFORMATION BFRO 296 /

7917 Technical Specification Involved Reported Under Technical Specification T.

S. 6.7. 2.b.4 Date of Occurrence 9/17/79 Time of Occurrence

Unct The total leakage was fdund to exceed the allowable 60% LA or 655.9 SCFH.

Total leakage was 3069.46 SCFH.

Conditions Prior to Occurrence:

Unit in cold shutdown for refueling.

Action specified in the Technical Specification Surveillance Requirements met NA uhit in cold shutdown.

~Aiarent Cause of Occurrence:

There was excessive leakage by valve seating surfaces.

~Anal aia ci'ccurrence:

No danger to health or safety of the public.

Corrective Action

The valves will be repaired and retested'to demonstrate compliance.

Failure Dat:a:

BFR0-50-260-7917.

~ ~Itet~ntion:

eriod - Lifetime; Responsibility - Administrative Supervisor

~Revision:

4

0 I

BFRO-50-296/7917 System involved:

Main Steam and Containment inerting.

Components Involved:

1-15, 1-26, 1-27, 76-17.

Component Failure:

Valve MFGR Size Type Model Mode of Oper.

Valve rating NOP Main Steam 1-14 1-26 1-27 Atwood

& Morrill Globe 20851 H

Air operated 1250 PSIG 8 575 F

1150 PSIG 8 562 F Containment Inerting 76-1'7 Worthington 2 II Butterfly 68-34212 Air operated 150 PSIG 8 PSIG-Leakage Path X-7A X-75 X-229f Isolation Valve 1-14/15 1-26/27 76-17 Path Leak Rate 433.9335 SCFH 1715.7145 SCFH 385.5555 SCFH NOTE:

1-14, 1-26, 1-27 previously reported for exceeding their allowable leak rate of 11.5 SCFH.

HLA:CJP 10/16/79