ML19269D543

LER 78-008/03L-0 on 780210:during Normal Plant Operation, Smoke Emanated from Supply Breaker for 13MOV131 Reactor Core Overload.Caused by Electrical Overload.Damaged Parts Replaced

ML19269D543
Person / Time
Site:	FitzPatrick
Issue date:	03/09/1978
From:	Pobutkiewicz S POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19269D542	List: ML19269D541 ML19269D543
References
LER-78-008-03L, LER-78-8-3L, NUDOCS 7906040227
Download: ML19269D543 (1)

Text

NRC FORM 366 U.S. NUCLEAR REGULATORY COMMISSION (7 77) ~ g -

. . . LICENSEE EVENT REPORT [)

. CON 1r10L BLOCK: l l l l l lh (PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) 1 6 7

0 1 8 9 l Nl YlJ l A l Fl 1 l@l LICENSEE CODE 14 O l 0 l -l O l Lf0CENSE 15 l 0 lNUMBER 0 l - l 0 l 0 l 0 25l@l264 l 1L3lCENSE 1 l 1TYPE l 1JOl@l57 CATl 58 l@

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5 uRC{ 60 l Ll@l 61 01 5 UCCKET l 0l 0Fi?JM8ER l 0 l 3 l 3 l 683 )@l 69 0121 1 l 017181@l EVENT DATE 74 75 013REPORTl 0 l DATE 9 I 7 l 880l@

EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h o 2 l During normal plant operation, smeke was eminating from the supoly breaker for I o 3 l 13MOV131, Reactor Core Isolation Coolant Turbine Steam inlet Valves. The breaker l o 4 l was tripped and the High Pressure Cooient injection Operability Test (ST-24F) was {

o s I satisfactorily performed. l Lo 6 I I o 7 l l o 8 l 7 8 9 80 E ODE S SC E COMFONENT CODE SUSCODE S E 7

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10 11 12 A l@ l R 13 l E l L l A l Y l X18l@ A 19

@ l 202l @

SEQUENTIAL OCCU R R E NCE REPORT REVISION LE R' AO EVENT YE AR REPORT NO. CODE TYPE N O.

@ ,R E l7l8l ll l0 0l8l lp] l0 [3 l l L] [] l0 l

._ 21 22 23 24 26 27 28 29 30 31 32 N ACT ON O PL NT ME HOURS 22 S8 1 FCR 8. SU IE MANUFA RER l33A lgl34X lg l5Elg l Z jg 3l7 0l0l0l l lNl@ l42Y l@ l43N ]@ l44G l0 l8 l047l@

3 36 40 43 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h i o l Electrical overload. Corrective action included reolacina 74 coll, 42XC coil and I i i I several ~Durnt wires with parts removed from a spare breaker. The Plant Ooerations i  : l Review Committee recommended replacing the existing relays with relays of hiaher I ii3 l voltage rating. l i 4 l 1 7 8 9 80 STA  % POWER OTHER STATUS DIS O Y DISCOVERY DESCRIPTION s NA Visual Routine inspection 1

[E_J@ l 0 l 7 l 9 l@l l lAl@l l ACTIVITY CO TENT-AMOUNT OF ACTIVITY LOCATION OF RELEASE 6 NA NA 7

1 AELEASt@oOFRELEASE@l 8 9 to 11 44 l l 45 80 l

PERSONNEL EXPOSURES NUM8ER TYPE D ESCRIPTION i 7 l0l0l0l@lZl@l NA l

' PERSONNE INJU IES i

~UM8ER oESCRIP1,0~e 2259 a'44 7

a 8 9 l0 lo l Ol@l12 11 NA 80 l

LOSS TYPE OF OR DAMAGE TO FACILITY Q D ESCRIPTION  %/

7 1 9 8 9 lEl@l 10 NA l 80 NR USE ONW ISSUE "' o'ESCRiPriON O 7906040 A77 7

2 o8 9lN hl to NA l 68 69 lllllllll11Ili, 80 3 NAME OF PREPARER PHONE: