ML19291C433

LER 79-022/01T-0:on 791226,safety Injection Pump B Failed to Start During Operational & Sys Leak Test.Caused by Incomplete Breaker Closure.Breaker Closed & Returned to Svc Following Cold Shutdown

ML19291C433
Person / Time
Site:	Point Beach
Issue date:	01/09/1980
From:	Fay C WISCONSIN ELECTRIC POWER CO.
To:	NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19291C431	List: ML19291C430 ML19291C433
References
LER-79-022-01T, LER-79-22-1T, NUDOCS 8001240427
Download: ML19291C433 (2)

Text

NRC Fog 4M 366 U. S. NUCLE AR GEGULATORY COMMISSION 0 774 LICENSEE EVENT REPORT CONTROL BLOCK: l 1

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(PLE ASE PRINT OR TYPE ALL REQUIRED INFORMATION)

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7 8 9 LICENSEE CODE 14 15 CON'T O 1 3[nc L@l 6101 5 l 010 l 0 l 2 6l6 68@!1 69 212 l 617 l 9 @l 0 REPORT EVENT DATE 74 75 l 1l 0 9l8l0l@

DATE 80 7 6 60 DOCK ET NUMBER EVENT DES ('RIPTION AND PROB ABLE CONSEQUENCES h safety iniection pump failed to

[o 2 lDuring steady state operation, the "B" I

o 3 lstart during an operational and system leak test because the power i o 4 l supply breaker did not completely close when the pump was returned to j o s Iservice following a cold shutdown of the unit 12-11-79. The unit was i O s Qaken critical at 1941 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.385505e-4 months <br /> on 12-22-79 and operated with one brief l 0 7 ishutdown until 0430 on 12-26-79 with only one safety iniection cumo l o 8 l operational because of incomplete breaker closure on the second pump. 30 I

7 8 9 SYSTEM CAUSE CAUSE C OV P. VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODE SUBCODE O 9 l S l F l @ [ A_j@ W @ l C l K l T B RjKl@ lAl@ W @ 2J 7 4 9 to in 12 13 is 13 SEQUENTt AL OCCURRENCE REPORT A E VISION u R RO EVENT YE AR REPOR T NO. CODE TYPE NO.

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43 44 W l ll 2l Ol@47 CAUSE D 'SCRIPTION AND CORRECTIVE ACTIONS h i O lWhen iliscovered, the incompletely closed breaker was completely clo ud I t i l i l land t' e safety iniection cump test was satisfacenrily cnmplotoa. mn it l>l lorevert future occurrence of this event, the safety iniection numo I W re tus;n to service procedure followino a cold shutdown will be mo6ified I

m lto i:tclude an operational check.

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NAME OF PREPARER C. W. Fav PHONE: 414/277-2811 {

ATTACHMENT TO LICENSEE EVENT REPORT NO. 79-022/OlT-0 Wisconsin Electric Power Company Point Beach Nuclear Plant Unit 1 Docket No. 50-266 On December 11, 1979, the unit was taken off line and placed in cold shutdown for steam generator eddy current inspection and tube plugging. As required by NRC, the pumps were removed from service by racking out the pump breakers to prevent the possibility of overpressurization of the reactor coolant system due to an inadvertent start of the pumps during the cold shutdown. The safety injection pumps were returned to service on December 22, 1979, prior to the unit being taken critical at 1941 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.385505e-4 months <br /> on the same day. Following a reactor trip before the generator was phased, the reactor was again taken critical at 0153 hours0.00177 days <br />0.0425 hours <br />2.529762e-4 weeks <br />5.82165e-5 months <br /> on December 23, 1979. The unit was placed on line at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on December 23, 1979, and was operating at steady state 78% power when the "B" safety injection pump failed to start during an operational system leak test at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on December 26, 1979.

Proper valve and electrical lineup was verified; however, investigation revealed that the power supply breaker was approxi-mately one inch open from its closed position, although the control room pump status lights indicated the breaker was closed.

The breaker was properly closed, and the operational system leak test was satisfactorily performed at 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> the same day. An operational test of the "A" safety injection pump had been satisfactorily completed prior to discovering the problem with "B".

Because of incomplete closure of the "B" safety injection pump breaker when returned to service, only one safety injection pump was operable when the unit was initially taken critical at 1941 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.385505e-4 months <br /> on December 22, 1979, and until discovery and correction of the problem at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> on December 26, 1979.

This violates Technical Specification 15.3.3.A.l.c and 15.3.3.A.2.a.

To prevent future occurrence of this event, the safety injection pump return to service procedure following a cold shutdown will be modified to include an operational check similar to that currently performed following any refueling outage or maintenance of the pumps.

The event is reportable in accordance with Technical Specification 15.6.9.2.A.2.

1794 144

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