05000259/LER-1981-033-03, /03L-0:on 810614,during Refueling,Total as-found Primary Containment Leak Rate Exceeded Tech Spec Limit. Caused by Deterioration of Valve Seating Surfaces During Operation.Valves Repaired

/03L-0:on 810614,during Refueling,Total as-found Primary Containment Leak Rate Exceeded Tech Spec Limit. Caused by Deterioration of Valve Seating Surfaces During Operation.Valves Repaired

ML20009F953
Person / Time
Site:	Browns Ferry
Issue date:	07/10/1981
From:	TENNESSEE VALLEY AUTHORITY
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML20009F947	List: 05000259/LER-1981-033-03, /03L-0:on 810614,during Refueling,Total as-found Primary Containment Leak Rate Exceeded Tech Spec Limit. Caused by Deterioration of Valve Seating Surfaces During Operation.Valves Repaired
References
LER-81-033-03L, LER-81-33-3L, NUDOCS 8108030191
Download: ML20009F953 (2)

LER-1981-033, /03L-0:on 810614,during Refueling,Total as-found Primary Containment Leak Rate Exceeded Tech Spec Limit. Caused by Deterioration of Valve Seating Surfaces During Operation.Valves Repaired

Event date:
Report date:
2591981033R03 - NRC Website

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EVENT DE5CRIPTION AND PDC 9 ABLE CONSEQUENCES h l o 12 l l During refueling operation, the total "as found" primary containment l anic rnea I

,g,,, ; exceeded T.S.4.7.A.2g allowable leak rate of 60 percent of La of 655.9 SCFH.

I gg,, l Total primary containment "as found" leak rate was 5997.5373 SCFH. There una l

l O I s 1 l no danger to the nealth or safety of the public. There were no redundant svstam=_

l [0l61gPrevious similar events: BFRO-50-259/80022, 79003: 260/78009. 79014. 8004%

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,o;,;;296/79017.

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101811 SYSTEM

CAUSE

CAUSE COMP.

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33 34 JS 36 31 40 41 42 43 44 47 CAUSE DESCRIPYION AND CORRECTIVE ACTIONS lijoll Leakage was caused by deterioration of valve seatina surfaces durine nnernHnn -

1 ggl Prior to returning to' power, valves will be reraired and retenrad un H 1 l

,,,7gj satisfactory leakage rates are obtained. Investigation of better merhnde en I

[il3l l control leakage continues, such as different valve seating materials. sentino I

I i 141 1 pressures, and closing times.

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• PCW E R OTHE R ST A TUS DISCO RY DISCOVERY OESCRIPTION NA l

lBl@l Surveillance testing l

11151 I "*1@ l 0 l 0 l 0 l@l ACTivt TY CO TENT RELEASED OF RELE ASE AYOUNT OF ACTIVITY LOCATION OF RELEASE l

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DESCRIPTION

1551 C D

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8108030191 810710 6s s,

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PDR ADOCK 05000259 c*

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Form BF 17 Tennessee Valley Authority BF 15.2 Browns Ferry Nuclear P' ant 6/04/81 LF.R S'JPPLEMEN I'AL INFuRMATION f

B F RC 259 / _81033___

Tuhaical Specu:# n In co!ved _4.7.A.2.g 7/14/81 6.7.2.b (4)

• Date due SRC:

Mcperted Under Tcchnical Sp cifie:itir n Date of Occurrence 6/14/81 Time of Occurrence 1000 Unit 1

Identification and_ I; esc _ription of Occurrence:

The total "as found" primary containment leak rate exceeded the 60 percent of La allowable leak rate of 655.9 SCFH. Refer to attachment 2 which details primary paths and leakage rates.

Conditions Prior to Occurrence:

Unit 1 - In refueling outage.

Unit 2 - At 71%.

Uuit 3 - At 98%.

Action specified in the Technical Specification Surveillance Requirements met due to inoperable ecu'inment.

Describe.

None yparent Cause af Oecurrence:

Deterioration of valve seating surfaces during operation.

Ana*.ysis of Occurrence:

There was no danger to the health or safety of the public, no release of and no resultine activity, no damage to the plant or equipment, significant chain of events.

Corrective Action

Valves will be repaired and retested until satisfactory leakage rates are Investigation of better methods to control leakage continues, obtained.

such as different valve seating materials, seating pressures, and -

closing times.

Failure Data:

BFRO-50-259/80022, 79003: 260/78009, 79014, 80049; 296/79017 Ijetention :

Pegl - Lifetime; Responsibility - Docw it Control Supervisor

• Revision :

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