05000348/LER-1979-036-03, /03L-0:on 790903,train B RHR Relief Isolation Valves Closed When Power Was Applied to Actuators to Enable Valve Position Indication.Caused by Pulled Fuses That Forced Output Circuit to Send Signal to Close Valves

/03L-0:on 790903,train B RHR Relief Isolation Valves Closed When Power Was Applied to Actuators to Enable Valve Position Indication.Caused by Pulled Fuses That Forced Output Circuit to Send Signal to Close Valves

ML19209A297
Person / Time
Site:	Farley
Issue date:	09/28/1979
From:	Hairston W ALABAMA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19209A294	List: 05000348/LER-1979-036-03, /03L-0:on 790903,train B RHR Relief Isolation Valves Closed When Power Was Applied to Actuators to Enable Valve Position Indication.Caused by Pulled Fuses That Forced Output Circuit to Send Signal to Close Valves 05000348/LER-1979-037-03, /03L-0:on 790906,auxiliary Bldg Battery Verification Was Two Days Late.Caused by Personnel Error. Performance of Surveillance Tests on Scheduled Dates Will Be Discussed W/Affected Personnel ML19209A293
References
LER-79-036-03L, LER-79-36-3L, NUDOCS 7910030487
Download: ML19209A297 (3)

LER-1979-036, /03L-0:on 790903,train B RHR Relief Isolation Valves Closed When Power Was Applied to Actuators to Enable Valve Position Indication.Caused by Pulled Fuses That Forced Output Circuit to Send Signal to Close Valves

Event date:
Report date:
3481979036R03 - NRC Website

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ALABAMA POWER COMPANY JOSEPH M. FARLEY NUCLEAR PLANT DOCKET NO. 50-348 ATTACHMENT TO LER 79-036/03L-0 Facilitv:

Joseph M. Farley Unit 1 Report Date:

9/28/79 Event Date:

9/3/79 Identification of Event:

Loop "B" RHR Rel ef 'sive Isolation Valves inadvertently closed during the ter srmance :: = aurveillance test.

Conditions Prior to Event

The unit was in Mode 5.

Descriptica of Event:

At 2200 on 9/3/79 while performing FNP-1-STP-11.7 (Verifying RHR Relief Valve Isolations are Open), the "B" Train RHR Relief Valve Isolation Valves (8702A and L) went shut when power was applied to the actuators to enable valve position indication. Tech. Spec. 3.4.9.3, in part, requires that valves 8702A and B be operable. Tech. Spec. 3.4.9.3 action statement requi-=~a"*s were met.

Designation of Apparent Cause:

A portion of the "B" train of the Solid State Protection System had been de-energized to allow implementation of the Feed Regulator Bypass Valve modification. The fuses that were pulled to de-energize the rack caused the output circuit to send a signal to close valves 8702A and B.

As soon as power was applied to the valve actuators the valves stroked shut and would not reopen.

Analysis of Event

The "A" Train RHR was operable and in servira The health and safety of the public were not affected.

Effect on Plant:

This occurrence had no significant effect on the plant.

1083 335

LER 79-036/03L-0

Corrective Action

The close signal was identified and cleared, and valves 8702A and 8 were reopened.

A design change has been submitted to evaluate a power for valve position indication from a different supply than valve actuarme power supply.

Failure Data:

None W*

- e+

9 1083 336

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