ML20010H882

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LER 81-048/03L-0:on 810808 & 25 Loop 1 Prestressed Concrete Reactor Vessel Cooling Water Outlet Temp Exceeded 120 F Due to Failure of Temp Controller.Caused by Cold Solder Joint & Failure of Transistor in Output Circuit,Respectively
ML20010H882
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 09/04/1981
From: Mcbride M
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML20010H873 List:
References
LER-81-048-03L, LER-81-48-3L, NUDOCS 8109290383
Download: ML20010H882 (1)


Text

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NRC FORM 366 U. S. NUCLEAR REGULATCQY COMMIS$ TON (111) ,

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REPOP.T DATE 80 i 8 60 61 DOCKET NUMBER 68 EV ENT D ATE EVENT DESCRIPTION ANJ PROBABLE CONSEQUENCES h tol2l l On August 8,1981, and again on August 25. 1981 with the plant ooeratine at 70% l goi3; l power, f ailure of a temperature controller resulted in Loop 1 prestressed concrete j i o 14 l l reactor vessel cooling water outlet temperature exceeding 120*F. Degraded mode of I

! I o l s i l LCO 4. 2.15. Reportable per Fort St. Vrain Technical Specific 1 tion AC 7.5.2(b)2. No l lo l6 l l accompanying occurrence. No effect on public health and safety. No previ'ous similar i i o I 71 l occurrence. l I

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3J 34 35 3d 40 el 42 43 44 47 CAUSE OESCRIPTION AND CORRECTIVE ACTIONS h s i t o l l he first event was due to a cold solder ioint in the Foxboro Model 62H-4E con P oiler. l

[TTi l i Tne second event in the sam controller was due to a failed transis tor in tha m- I g,i7; l troller output circuit. He solder j oint was repaired. and and the transis tor n-7 wasl y ] replaced to restore the controller to service. l 1

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LOSS OP OR OAMAGE TO PACILITV TYPE DCSCRIPTION

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