05000321/LER-1980-111-03, /03L-0:on 801106,automatic Depressurization Sys Reactor Water Level Switch 1B21-N042A Actuated Above Tech Specs.Caused by Component Failure Due to Galling of Range Adjusting Screw.Level Switch Replaced

/03L-0:on 801106,automatic Depressurization Sys Reactor Water Level Switch 1B21-N042A Actuated Above Tech Specs.Caused by Component Failure Due to Galling of Range Adjusting Screw.Level Switch Replaced

ML19345B495
Person / Time
Site:	Hatch
Issue date:	11/24/1980
From:	Nix R GEORGIA POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II)
Shared Package
ML19345B481	List: 05000321/LER-1980-111, Forwards LER 80-111/03L-0 05000321/LER-1980-111-03, /03L-0:on 801106,automatic Depressurization Sys Reactor Water Level Switch 1B21-N042A Actuated Above Tech Specs.Caused by Component Failure Due to Galling of Range Adjusting Screw.Level Switch Replaced
References
LER-80-111-03L-01, LER-80-111-3L-1, NUDOCS 8012010394
Download: ML19345B495 (2)

LER-1980-111, /03L-0:on 801106,automatic Depressurization Sys Reactor Water Level Switch 1B21-N042A Actuated Above Tech Specs.Caused by Component Failure Due to Galling of Range Adjusting Screw.Level Switch Replaced

Event date:
Report date:
3211980111R03 - NRC Website

text

LICENSEE EVENT REPORT d

CONT Hol BLOCK: l l

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lh (PLE ASE PntNT CR TYPE ALL REQUIRED INFORMATION) 1 6

l G l A l E lI lH l1 l@l 0] 0l -i 010] 0] 0l 0l -l 010]@l 4l Il ll 1l 1l@l l

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8 9 LICENSEE CODE 14 15 LICENSE NUMuEH 25 26 LICENSE TYPE JO 5 7 C A T bd S% l t l@l 01 5I O! 01 0] 3l 2l 11@l 1l 11 016l 81 0]@l li 1l 2I 418 l 0 l@

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60 61 DOCKET NUMGER 68 69 EVENT DATE 74 75 REPORT DATE 80 EVENT oESCRIPTloN AND PROBABLE CONSEQUENCES h lo 121 l While the plant was in steady state operation at 1870 ffAt,1821-N042A, l

1013 l l ADS Reactor Water Level Switch, actuated at 83" H 0 input,

<0" level.

l 2

I O 14 I l Tech Specs section 3.2-4, Item 1, requires setpoint to be ?+12.5" level.

I lo is] l Redundant switch IB21-N042B was operable.

Plant operation was not affect-l 10 is i I ed.

Public health and safety was not affected by this event.

This is l

l0l7ll a non-repetitive event.

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l 80 7

8 9 C DE CODE SU8CO E COMPONENT CODE SUBC dE SU E

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9 10 11 12 13 ta 19 20 SE QUE NTI AL OCCUR R E NCE REPORT REVISf0N LER RO EVENT YEAR REPORT NO.

CODE TYPE N O.

O y,gRT l 8l 0l l-l l 1l 1] 1l l/l l0l3l lL l l-l W

_ 21 22 23 24 26 27 28 29 JO 31 32 O

AKEN A ON O PL NT MET +

HOURS S BNIT D FO A1 8.

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33 34 36 36 31 40 41 42 43 44 47 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS li lOI I The cause of this event was component failure.

The failure was due to l

11 111 I qalling of the range adjusting screw.

The Yarway level switch was replaced.

1 i 7 l The replacement was functionally tested satisfactorily.

The unit is now l

13l3l l in full compliance and no further reporting is required.

l l i 141 I l

7 8 9 80 ST S

% POWE R OTHER STATUS ISCO RY DISCOVERY DESCHIPTION W @ l 0] 7l 7l@l NA l

l B l@l Surveillance Test l

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e 80 COTTENT ACTIVITY RELE ASED Of HELE A3E AMOUNT OF ACTIVITY LOCATION OF RELEASE l lc l [Zj @ l Zl@l NA l

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7 8 9 10 11 44 4S 80 PE RSONNEL E nFCSURES NUMBE R Y' PE

DESCRIPTION

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,ERSONNi L,N;u'JitS oE SCn,P T,0~@

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8 9 11 12 80 LOSS OF OR DAYAGE TO F ACILITY TYPE DE SC RIP 110N W @l NA l

7 8 9 10 80 PUBtlCITY NRC UsE ONLY

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7 H 9 10 G8 69 80 &

R. T. Nix, Supt. of Maintenance EEN g

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LER No.: 50-321/1980-111

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Licensee:

Georgia'. Power Company

- Facility Name: Edwin I. Hatch Docket No. : 50-321

Narrative

Report for LER !!o. 50-321/1980-111 On November 6,1980, with the plant in. steady state operation at 1870 f1Wt, 1821-N042A,- ADS Reactor Water Level Switch, actuated at 83" H 0 input, 2

<0" H 0-level.

Tech Specs section-3.2-4, Item 1, requires the setpoint 2

to be 2+12.5" H2O level.

Redundant switch 1821-N042B was operable. Plant operation was not _affected.

The cause of the event was component' failure.. The failure' was due to galling

. of the range adjusting screw. The yarway level switch was Ereplaced. The new switch was functionally tested. satisfactorily.

A generic review revealed no inherent problems.

Public health and safety

- was not affected. The unit is now in full compliance with the requirements I

and no further reporting is required.

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