ML19338E076

LER 80-055/03L-0:on 800821,motor Overload Alarm Was Received on Mo 1301-62 Valve in Reactor Cooling Isolation Sys.Caused by Valve Thermal Overload Device.Evaluation of Capacity Rating of Overloaded Device Being Conducted

ML19338E076
Person / Time
Site:	Pilgrim
Issue date:	09/19/1980
From:	Mcloughlin M BOSTON EDISON CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
Shared Package
ML19338E075	List: ML19338E074 ML19338E076
References
LER-80-055-03L, LER-80-55-3L, NUDOCS 8009240468
Download: ML19338E076 (1)

Text

. . .

n; 8 i /. LICENSEE EVENT REPORT

, CONTROL BLOCK: l i

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(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATIONI l 158l@

l l o 11 7 -8 9 l l Ml ' Al' LICENSEE P l P l S l 1l@150uCENSE CODE 14 l 0 NUM8ER l -l 0 l 0 l 0 l 250 ] 26O l -LICENSE l 0 lTYPE 0 l@lJO 4 CAT 57 l1l1l1 CON'T l0l1l Qu' "C l60Ll@l 610l- 5 l 0OoCKET l -l 0NUMBER l 2 l.9 l 3 @l 069 l 8 lEVENT 2 l 1DATEl 8 l 0 l@l 0 l 9REPORTl 1 l DATE 9 l 8 l 080l@

7 8 68 74 75 EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h l0l2l l On August 21, 1980 at approximately 0440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br /> while performing surveillance test l

,o,3, l #8.5.5.4 on the RCIC. system a motor overload alarm uns received on MO 1301-62 valve. l 10141 1 Investigation revealed the protective alarm was generated by the valves thermal overlokd Io isl I device which is utilized for annunciation only. Automatic ope'ation of the valve was l 10 is I I still available. Until an investigation of the cause of the alarm was comcleted, I I ITT71 I manual operation of the valve was utilized. Following maintenance, the valve was I i

i O l s I l tested and the RCIC system was returned to service. I 7 8 9 80 0E CODE S BC E COMPONENT CODE SUSCOdE S E lol9l 7 8

'l Cl El@ l Xlh l Z lh lX lX lX IX lX lX lh i Zlh W h 9 10 11 12 13 18 19 20 l

_ SEQUENTI AL OCCURRENCE REPORT REVISION I LE R/Ro EVENT YE AR REPORT NO. CODE TYPE N O.

h ,RE_P g l-l l0 l5 l5 l l/l 10 l3 l lLl l-l l0 l

_ l218 22l0 l 23 24 26 27 28 29 30 31 32 K N AC 0 0 P T ME HOURS S8 i FOR 8. SUPPLIE MANUF C RER lAl@lX!@

33 34 lZl@

3b l36 Z lh 3l1010l0l0l40 lN l@ 41 lN 42 l@ lN 43 l@ lT 44 l1 l4 l747l@

CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h l gilOj l The valve's Westinghouse thermal overload device was replaced. Analysis indicates 1 1 g ] that the thermal overload rating is approximately 1.0 ampere. The valve motor coeratot-

,,,,, jat approximately 1.3 amperes. Evaluation of the capacity rating of these devices is l li;3glbeing reviewed. No failed component was identified however as a precaution the l

,,,,, ;above device was replaced.  ;

7 8 9 80

$A  % POWER OTHER STATUS I O ERY DISCOVERY OESCRIPTION I i l 5 l Wh l1 l 0 l 0 l@l N.A. l lBl@l Surveillance Testing l l

ACTIVITY CO TENT EELEASED OF RELE/* AMOUNT OF ACTIVITY LOCATION OF RELEASE I116I W @lZlh N.A. l l N.A. l PERSONNEL EXPOS ES NUMSER TYPE DESCRIPTION l 1 l *7 l l 0 l 0 l 0' lhWhl 7

N.A. l

' PERSONNEL INJUIES NUMBER DESCRIPTION l1 7

la8l 9l 0 l 0 l 0 l@l12 11 N.A. l 80 LOSS op OR DAMAGE TO FACILtTV TYPE OESCRIPTION l7 t l 989l l Z l@lto N.A. l 80 NRC USE ONLY ISSUE DE CRIPTION @ 8 009240 Q ,

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7 8 9 hl - 10 N.A. l 68 69 lllllllllllll{ 80 ~n m.

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' NAME OF PREPARER

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