ML20054G876
ML20054G876 | |
Person / Time | |
---|---|
Site: | |
Issue date: | 06/09/1982 |
From: | Dickey F Public Service Enterprise Group |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
Shared Package | |
ML20054G858 | List: |
References | |
LER-81-035-03X, LER-81-35-3X, NUDOCS 8206220375 | |
Download: ML20054G876 (1) | |
Text
NRC F07.M 366 U. S. NUCLEA"3 REOULATEY COMMISSION 17 77)
LICENSEE EVENT REPORT CONTROL BLOCK: l I
l l l l l lh 6
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION) lo Iil8 lN i 9 lJ LICENSEE lS l Gl COOE Sl1 l@lIS 0 l 0 l -l 0 UCENSENuYSER 14 l 0 l 0 l 0 l 0 l - l 025l 0 26l@l4 l1lll1l1l@l5 7 C lA T $8l@
uCENSE TYPE Jo 1
C ON'T lol11
? 8 TR$lL@l0l5l0l0 s
60 $1 l 0l 2l 7 l 2 @l 0 l69 3 l EVENT OOCKET NUMBER 68 2 l 2OATEl 8 l 1 @l 0l 6l 0l 9l 8l 2l@
74 75 REPORT O ATE 80 EVENT DESCRIPTION AND PROB ABLE CONSEQUENCES O'o
- g,;, ; During the performance of Surveillance Test SP(O)4.0.5(V) on 3/22/81, it was dis- g
- covered that the Number 11 Safety Injection Pump Discharge Valve llSJ40 would not g
,g,,, g open. Action Statement 3.5.2.a was entered at 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />. Investigation revealed i
,o;3y;a missing wire in the valve's control circuit. The wire was replaced and the i g l Action Statement terminated at 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on 3/22/81. Previous to this event, the l -
l 0 t 7 l I valve's control circuitry had undergone modification to provide a console controllect t O le l Ilockout feature. 8o I
r 8 ,
SYSTEY CAUSE CAUSE C OYP. VALVE CODE CODE SUSCODE COMPONENT CODE su8 CODE SU8 CODE l0l9l l Sl Fl@ yh Wh l Il Nl Sl % Pl Qh Wh Wh 20 7 8 9 to 11 12 13 18 19
,_ SE QUENTI AL OCCURRENCE REPORT R EVISION LE R *O EVENTYEAR REPORT NO. CODE TYPE N O.
O",af RT l8 l1l 25 22 l-l 23 l 0l 3l 5l 24 26 l/l 27 l0 l3 l 3 29 lX l 30 b
31 W
32 EN A ON O PL NT MET MOUR$ 58 i FOR B. $UPPLI E MANUFACTURER W@W@ lzl@
33 34 3S Wh 36 3l7 0 l0l0l0l 40 Wh 41 lNl@
42 lL 43 l@ l44M l 3 l 0 l 247 l@
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS h IiIUll Tests to verify the lockout function of the valve were not performed in accordance I y l with instructions contained in the Design Change Package. In order to preclude I g l recurrence, Administrative Procedure AP-8 was chancred to require work supervisor I l Ia1iand department head signatures after the required testing. l Li L_j l I 7 8 9 So STA S % POWER OTHER STATUS O50 RV OISCOVERY OESCRIPTION N/A Operator Observation l l i l 5 l W@ l 1 l 0 l 0 l@l l l B l@l ACTtvtTV CO TENT RELEASEO OFRELEasE AMOUNT OF ACTivtTY LOCATION OF RELEASE l1 l6l hlzl l N/A l l N/A l 7 8 9 10 31 44 45 80 PERSONNEL exposures NuveER TvPE DESCRIPTION lM l' 0' l 010 l@l zl@l
n/A l
,E RsONN E'L ,N;U4 Es NUYS E R DESCRIPTION li la 8i 10l 7 9 010l@l1211 N/A 80 I
LOSS TvPE OF OR O AM AGE TO FACILITY h DESCRIPTION v ITTTI* *I z l@l'o N/A I 8
,"'* 8206220375 820609 NRC USE Om OEsCR , TION @ PDR ADOCK 05000272 ,
2 O issudtLt 81 N/A s poR i i i iiiiilii iiig 7 8 9 to 68 69 80 3 NAME Of PREPARER
. Chy PHONE:
(609) 541-5900 629 E
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