05000293/LER-1980-055-03, /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

/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: 05000293/LER-1980-055, Forwards LER 80-055/03L-0 05000293/LER-1980-055-03, /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
References
LER-80-055-03L, LER-80-55-3L, NUDOCS 8009240468
Download: ML19338E076 (1)

LER-1980-055, /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

Event date:
Report date:
2931980055R03 - NRC Website

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LICENSEE EVENT REPORT CONTROL BLOCK: l l

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LICENSEE CODE 14 uCENSE NUM8ER 25 26 LICENSE TYPE JO 57 CAT 58 CON'T l0l1l Qu' "C l Ll@l 0l 5 l 0 l -l 0 l 2 l.9 l 3 @l 0 l 8 l 2 l 1 l 8 l 0 l@l 0 l 9 l 1 l 9 l 8 l 0 l@

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OoCKET NUMBER 68 69 EVENT DATE 74 75 REPORT DATE 80 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

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.

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8 9 80 0E CODE S BC E COMPONENT CODE SUSCOdE S

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10 11 12 13 18 19 20 SEQUENTI AL OCCURRENCE REPORT REVISION LE R/Ro EVENT YE AR REPORT NO.

CODE TYPE N O.

h,RE_P g l218 l0 l l-l l0 l5 l5 l l/l 10 l3 l lLl l-l l0 l 22 23 24 26 27 28 29 30 31 32 K N AC 0 0 P T

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40 41 42 43 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h gilOj l The valve's Westinghouse thermal overload device was replaced.

Analysis indicates 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.

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% 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

ACTIVITY CO TENT EELEASED OF RELE/*

AMOUNT OF ACTIVITY LOCATION OF RELEASE I116I W @lZlh N.A.

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l PERSONNEL EXPOS ES NUMSER TYPE

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' PERSONNEL INJU IES NUMBER

DESCRIPTION

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8 9 11 12 80 LOSS op OR DAMAGE TO FACILtTV TYPE OESCRIPTION l t l 9 l l Z l@l N.A.

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89 to 80 DE CRIPTION @

8 009240 Q NRC USE ONLY ISSUE M

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