ML19352B175

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LER 81-025/03L-0:on 810317,loss of Electrical Power to Liquid Nitrogen Storage Tank Resulted in Tank Level Decreasing Below 650 Gallons.Caused by Circuit Breaker Tripping on Overload So That Fill Valve Closed
ML19352B175
Person / Time
Site: Fort Saint Vrain Xcel Energy icon.png
Issue date: 04/16/1981
From: Gahm J
PUBLIC SERVICE CO. OF COLORADO
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV)
Shared Package
ML19352B170 List:
References
LER-81-025-03L, LER-81-25-3L, NUDOCS 8106030263
Download: ML19352B175 (1)


Text

NRC pored 308 ,

U. S. NUCLEAR RE:ULATORY COMmelSS40N (7 "77) 'e -

LICENSEE EVENT REPORT CONTROL SLOCK: l l l l l l (PLEAss PRINT OR TYPE ALL REQUIREO INFORMATION)

I l o uCENsE 101010 l o l- lo l oes l@l26 4 liuCENst ll l 2101@l I l l lo li la Isc l ouCENs.E l v l sCOct I v i i l@ltso l o l i4 NuMeER tveE 40 si ear se @ l CON'T Iol'l 7 4 sour lL @l0l5l0l010]2l617 @l01311l7l811l@l01411l618l1l@

60 61 DOCKET NUMeER 68 69 EVENT DATE 74 is REPORT DATE do EVENT DESCRIPTION ANO PRC8ASLE CONSEQUENCES h I

E I local loss of electrical oower to liould nirroosn s rar nam " n lr room resultad in

["5"TTl j storage tank level decreasing below 650 gallons. A minimum level reached was 600 gal-l lolalIlons. Degraded mode of LCO 4.2.12. Reportable per Fw;t St. Vrain Technical Specif1- I l o I s l l cation AC 7.5.2(b) 2. No accompanying occurrence. No effect on public health or l lo is l l safety. Similar occurrences RO 81-020.81-011. and 80-39. I l

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I o liii l 60

' E CODE SUSC E CCMPONENT CODE Sue 00E $ E o 9 l Al Dl@ {,Bj@ l A l@ lC lK lT lB lR lK l@ ]@ Q @

13 16 19 20 F 3 9 io 3: 12 SEQUENTtAL OCCURRENCE REPORT REvts10N EVENT VEAR REPORT NO. CODE TYPE NO.

Eg I 81 11

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i4 47 CAUSE DESCRIPTION ANO CORRECTIVE ACTIONS h l i l a l 1120V circuit breaker tripped on overload causing temoorary control system for licuid I li!ii initrogen storage tank to close fill valve. Breakgr was reclosed and level re-estab- I g llished to normal. Modification made to defeat temporarv control system if local 1

, 3 l electric power is lost to allow fill valve to be ooened. Nitrogen system being i lii4i l evaluated by PSC Nuclear Projects Department. Results will be suoplied in a future 1 7

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  • sTe rui .s CMR oTHEa status @

METw00 Or eiscovERv oiscovERv oEsCRipriON h i l1 I 5 l Wh l 0 l 6 l 9 lhi N/A l l A l@l Coerator Observation ACTtvlTV CC TENT RELEASED OPRELEA$E AMOUNT OF ACTIvlTV LOCATION OF RELEASE l I N/A l l1 16I W h W' @ l N/A

  • PERSONNEL EXPOSu ES t NuueER TveE oEsCRietiOs h l

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  • ERsoNNEi.'iNau' des NUMBER DESCRIPTION @

l, '_j,4,,j l 0I ol Olhl N/A so I

F es si 12 LOSS OF OR DAMAGE TO FACILITY Q TY8E CEsCRIPTION V

[t_]y,,J [Z_j@l N/A l go ,

7 4 3 to NRC usE ONLY ,

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7 4 7 68 69 30 ;

NAME OF PREPARER A 1\ M PHONE:

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