05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel

/03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel

ML19344D328
Person / Time
Site:	Davis Besse
Issue date:	03/06/1980
From:	Werner J TOLEDO EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19344D327	List: 05000346/LER-1980-013, Forwards LER 80-013/03L-0 05000346/LER-1980-013-03, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel
References
LER-80-013-03L, LER-80-13-3L, NUDOCS 8003110685
Download: ML19344D328 (2)

LER-1980-013, /03L-0:on 800208,w/reactor Startup in Progress, Personnel Noted Control Rod 5-11 Absolute Position Indication Was Not Responding.Caused by Blown Fuse F14 in Position Ref Panel

Event date:
Report date:
3461980013R03 - NRC Website

text

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EVENT oATE 74 75 REPORT DATE dQ EVENT DESCRIPT10'4 AND PROS ABLE CONSEQUENCES h it was noted that control ;

] io l a l l On 2/8/80 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> with a reactor startup in progress,

~ I o Ia l I rod 5-11's absolute position indication (API) was not responding. The reactor startup; The reactor startup was g

[ I o l a 1 1 was terminated and all group 5 control rods were driven in.

the limiting conditions of T.S. 3.0.4,whicy

[ [o l s i l terminated because the unit could not meet [Z I o Ic l l required the unit to meet T.S. 3.1.3.3 prior to going into Mode 2.

There was no dangeq l 0 l 7 l l to the public or station personnel. The control rod never deviated from its intended ;

l o lc l l Position in the group, only the API was faulty.

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- li l o l l The apparent cause was that fuse F14 in the position reference panel for Control Rod l

[ lTTT] l 5-11's 5 VAC API supply was blown.

Fuse F14 was replaced and the API module voltages l

[ li l 21 I were checked satisfactory.

Control Rod 5-11 was withdrawn to verify the API was track 7 Z 1,131 l ing.

The API was declared operable and able to meet T.S. 3.1.3.3 for Mode 2, and the [

I reactor startup was commenced.

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TOLEDO EDISON COMPANY DAVIS-BESSE NUCLEAR POWER STATION UNIT ONE SUPPLEMENTAL INFORMATION FOR LER NP-33-80-20 DATE OF EVENT:

February 8, 1980

~ FACILITY: Davis-Besse Unit 1 IDENTIFICATION OF OCCURRENCE: Control Rod 5-11 Absolute Position Indication (API) fuse failure Conditions Prior to Occurrence: The unit was in Mode 3, with Power (MWT) = 0, and Load (Gross MWE) = 0.

4 Description of Occurrence: On February 8, 1980 at 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> with a reactor startup in progress, it was noted that control rod 5-11's API was not responding. Control rod movement was verified by actuating one of the rod's zone reference lights. The Since reactor startup was terminated and all group 5 control rods were driven in.

the unit was in Mode 3, Technical Specification 3.1.3.3 covering control rod API's in Modes 1 and 2 did not apply. The reactor startup was terminated because the unit could not meet the limiting conditions of Technical Specification 3.0.4, which required the unit to meet Technical Specification 3.1.3.3 prior to going into Mode 2.

Designation of Apparent Cause of Occurrence: Blown fuse F14 in the position refer-ence panel for Control Rod 5-11's SVAC API supply.

Analysis of Occurrence: There was no danger to the health and safety of the public 3

or to station personnel. The control rod never deviated from its intended position in the group, only the API was faulty.

Corrective Action

Fuse F14 was replaced, and the API module voltages were checked satisfactory. Control rod 5-11 was withdrawn to verify the API was tracking. The API was declared operable and able to meet Technical Specification 3.1.3.3 for Mode 2 and the reactor startup was commenced.

Failure Data: There have'been previous failures of control rod APIS but no apparent failures due to this fuse.

LER #80-013 l

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