05000280/LER-1980-045-03, /03L-0:on 800713,during Steady State Operation at 100% Power,Leak Discovered Through Valve 1-BR-236 Which Resulted in Unsampled Release.Caused by Leaking Diaphragm Valve.Maint Rept Issued for Repair of Valve

/03L-0:on 800713,during Steady State Operation at 100% Power,Leak Discovered Through Valve 1-BR-236 Which Resulted in Unsampled Release.Caused by Leaking Diaphragm Valve.Maint Rept Issued for Repair of Valve

ML18139A613
Person / Time
Site:	Surry
Issue date:	07/29/1980
From:	Joshua Wilson VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.)
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML18139A612	List: 05000280/LER-1980-045, Forwards LER 80-045/03L-0 05000280/LER-1980-045-03, /03L-0:on 800713,during Steady State Operation at 100% Power,Leak Discovered Through Valve 1-BR-236 Which Resulted in Unsampled Release.Caused by Leaking Diaphragm Valve.Maint Rept Issued for Repair of Valve
References
LER-80-045-03L-01, LER-80-45-3L-1, NUDOCS 8008040151
Download: ML18139A613 (2)

LER-1980-045, /03L-0:on 800713,during Steady State Operation at 100% Power,Leak Discovered Through Valve 1-BR-236 Which Resulted in Unsampled Release.Caused by Leaking Diaphragm Valve.Maint Rept Issued for Repair of Valve

Event date:
Report date:
2801980045R03 - NRC Website

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REPORT DATE 80 state 1 at 100% power an operator discovered a leak through in valve l-BR-236.

This caused an unsampled release during the release of l-BR-TK-2A.

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SURRY POWER STATION UNIT NO...,

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50-280 REPORT NO:

80-045/031-0

~VENT DATE, 07-13-80 TITLE OF REPORT:

UNSAMPLED BORON RECOVERY TEST TANK RELEASE

1.

Description

of Event:

During steady state operation of Surry Unit No. 1 at 100% power an operator discovered that the isolation valve (l-BR-236) for l-BR-TK-2B was leaking through during the release of l-BR-TK-2A, thereby causing an unsampled release:fro~ Tank B.

2.

Probable Consdquences/Status of Redundant Systems:

The release was evaluated and detennined to be 0.012% of the Tech. Spec. Limits.

Effective concentration in the discharge canal was so low that the radionuclides may be consided as not present per 10CFR 20.

The flow path and flow rate were being monitored by the installed instrumentation.

The system had the capability to stop the flow to the discharge canal header if the activity in the discharge line exceeded the set point for the radiation monitor.

Therefore the health and safety of the public were not affected.

3.

Cause of Event

The cause is detennined to be due to the leakage of the diaphragm valve.

Immediate Corrective Action

Further release was terminated.

A Maintenance Report was initiated to repair the valvei.

5.

Scheduled Corrective Action:

Repair the valve.

6.

Action Taken to Prevent Recurrence:

7.

Administative controls have been established to insure sampling of both tanks prior to connnencing any release.

Generic Implications.

A program for the routine inspection of the valves (MMP-C-V-001) is in effect.

The diaphragms and other components that do not pass the inspection are being replaced.

The diaphragms of the valve in question was replaced on May 12, 1980.

The valve was found to be leaking on June 10, 1980.

It was repaired on June 26, 1980, and it was determined to be a random event.

Because of the current event maintenance requests have been initiated to inspect all (six),-.. valves between the two tanks to determine. Generic Irnpli~ation*~-.