ML19259C692

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LER 79-013/031-0 on 790712:while Performing Motor Operated Valve Operability Test,Thermal Overload Relay for Pump Suction Valve 1C RHR Tripped & Could Not Be Reopened.Caused by Loose Electrical Connections at Breaker
ML19259C692
Person / Time
Site: Quad Cities Constellation icon.png
Issue date: 08/03/1979
From: Hoeller J
COMMONWEALTH EDISON CO.
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION III)
Shared Package
ML19259C690 List:
References
LER-79-013-03L-05, LER-79-13-3L-5, NUDOCS 7908140588
Download: ML19259C692 (1)


Text

NRC FORM 366 U. S. NUCLEAR REGULATORY COMMISStoN (7 77) ' .

LICENSEE EVENT REPORT CONTROL BLOCK: l l l l l l (PLEASE PR!NT OR TYPE ALL REQUIRED INFORMATION)

I d lo 1 l1 L l Q l A l D l 2 l@l 0 l 0 ' O l - l0 l 0 l 0 l - l 0 l 0 ] O l@l 4 1ll l1l1 @l l@

8 9 LICENSEE CODE 14 15 LICENSE NuveER 25 26 LICENJE TYPE J0 b7 GAT bd CON'T REPOA o i 3c 9C L l@l 0 l 510 j 0 l0 l2 l615 l@l 0l 71 1 l 217 l 9 }@l 0 [ 8 [ 0 l 3 l 7 ( 9do l@

7 a 60 61 DOCKET NUMBER 68 63 EVENT DATE 74 75 REPORT CATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES h a 2 l While performing the LPCI Motor Operated Valve Operability Test. QOS 1000-3. the I go;3g l thermal overload relay for the normally open IC RHR pump suction valve, M0 2-1001-7C, l o 4 l tripped and the valve could not be reopened after closure (T.S.3.5.3). The survell- I o s lance requirements of T.S.3.5.4 were started. The valve was demonstrated operable I a s l prior to completion of all surveillance items. The other three RHR pumps for the LPCI l 0 7 l mode and the Core Spray Sub-system were available. If necessary the valve could have l g g  ; been manually opened. l 7 8 9 80 SYSTEM CAUSE CAUSE COMP. VALVE CODE CODE SU8 CODE COMPONENT CODE SU8 CODE SUSCODE M7 8 l S l F j@ g@ l Al@ lC lK lT lB lR lK l@ l Bl@ W @

9 10 20 11 12 13 18 19 SEQUE NTI AL OCCURRENCE REPORT REVislON

_ EVENT YE AR REPORT NO. CODG TYPE NO.

@ ,"Lu'M ERJR O 91 I 71 l--I I Ii 3 l'l I 13 1'I l- UI

_ 21 22 23 24 26 27 28 23 30 31 32 T KE A TC ON PLANT T D HOURS S B IT D FOR B. SU PPI.l E MANUFACTLRER

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33 J4 l35Z l@ l36Z l@ l 0 l 0 l 0 l 0,1 31 40 W@

41 lH l@ lN l@ lG l 0 l 8 l O47 l@

42 43 44 CAUSE DESCRIPTION AND CORRECTIVE ACTIONS 27 i o lAlthough an exact cause could not be determined. Investications eerformed indicated a l i i tprobable cause to be loose electrical connections at the breaker. The toraue and I

, 7 l limit switches were not defective. Corrective action was to check and tighten i 3 [ electrical connections and to take operating motor current measurements during sub- 1 i 4 l sequent valve operability exercises. Motor currants were found to be normal. I

? a 9 80 A  % POWER # CTHER STATUS 15 RY DISCOVERY OESCRIPTION l ' 15 l l_E jg l 0 l 7 l0 lgl NA l l8[glRoutineTest l ACTIVI TY C TENT RELEASED OF RELE ASE AMOUNT OF ACTIVITY LOCATION OF RELEASE ylZ 7 3 3 l @ l Z jgl to i1 NA 44 l l 45 NA 80 l

PERSONNEL EXPOSURES NUVBER TYPE DESCRIPTION i 7 l 0l 0 0l@lZl@l l PERSONNE L INJURIES NUVBER C E SCRIPTION ji 7

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0l0l0l@l 11 12 NA 80 l

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9

'r$'E NA 7 90814 05W 7 d 9 l Z l@ 10 l y . . ' , .' 30 PU B LICI T Y s,(J L LJ. ' '

ISSUED DESCRIPTION NRC USE ONLY 1 loj l N j o5'l NA { llllllll ll l 1l$2 J. Hoeller W4%4hl

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