LER-1987-004, Forwards LER 87-004-01 Detailing Loss of Red Instrument Bus During Replacement of Battery Cell.Encl Delayed Due to Depth of Investigation |
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(414) 221 2345 Beach instrument ery and
)(iv), "Any tomatic eluding the is h of the We discussed 0
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,<<yr Wisconsin Electiic,'>>0kiR;cggp,jj, 231 W. MICHIGAN,P.O, BOX2046, QILWAUI<EE,WI 5320't VPNPD-87-511
"'","'.",'0 CFR 50.73 NRC 87 118 i", ','..
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I November 20, 1987',-'
I It U. S.
NUCLEAR REGULATORY'(COMMISSION)','ocument Control
.Deski~'ashington, D.
C.;>;20555I I
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II1'entlemen:
DOCKET 50 266 yg "'"'
'ICENSEE EVENT REPORT'<87-004-'1><
LOSS OF THE RED INSTRUMENT'>BUSl.
POINT BEACH NUCLEAR'<PLANT'">>UNIT<1;
Attached is Licen*seel'Eve1nt<Report',j87.=,004-01, for Point Nuclear Plant, Unit~'1,,:;detailiiig th'e~>loss of the red bus during a replace>>mentt!:,'of".(a>,'bat:teiyi',cell.
The batt associated DC bus'"are,ctommon',-to~+both~'units.
II LER 87-004-01 is filed'~pursuant'>to~'(10i.CFR
'50. 73 ( a) ( 2 operation or condition,'1that'<resulted~~",in manual or au actuation of any engineeredl)safety'Ifeature (ESF), in reactor protection.,systems,';(RPS);'I" We had noted in the"original'".LER'>>;that-'~we>>expected th supplement to be filed',",by.10ct>>tobe',!1';; ~1987.'he dept investigation has'aused'jth'e>~r'epo4rt
'<to'~1be 'delayed.
the timing with the senior4Residen011Inspector.
If any further information. i',,',required; please contact us.
Very truly yours, i /
4./
C.
W. Fay Vice President Nuclear Power w
Enclosure Copies to NRC Resident,Inspi ctor.',
NRC Regional Admini1stiator; 'Region III erat.~t02>>g 87>>>>2,Igt, 8
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| 05000266/LER-1987-001-01, :on 870404,unit Manually Tripped After 22 Control Rods Dropped.Reactor Engineer Incorrectly Connected Leads Shorting Out Test Instrument.Mods to Test Equipment to Prevent Hookup Errors Evaluated |
- on 870404,unit Manually Tripped After 22 Control Rods Dropped.Reactor Engineer Incorrectly Connected Leads Shorting Out Test Instrument.Mods to Test Equipment to Prevent Hookup Errors Evaluated
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000301/LER-1987-001, :on 870205,steam Flow/Feedwater Flow Mismatch Setpoint for Reactor Trip Found in Violation of Tech Spec. Caused by Failed Electrolytic Capacitor in Square Root Converter Module FM-475B.Module Repaired |
- on 870205,steam Flow/Feedwater Flow Mismatch Setpoint for Reactor Trip Found in Violation of Tech Spec. Caused by Failed Electrolytic Capacitor in Square Root Converter Module FM-475B.Module Repaired
| 10 CFR 50.73(a)(2)(1) | | 05000301/LER-1987-002-01, :on 870816,reactor Trip Occurred.Caused by Lightning Strike to Transmission Line Associated w/2X01 Transformers or Ground Near Transformers.Damaged Corona Ring of 2X01 Phase B Transformer Repaired |
- on 870816,reactor Trip Occurred.Caused by Lightning Strike to Transmission Line Associated w/2X01 Transformers or Ground Near Transformers.Damaged Corona Ring of 2X01 Phase B Transformer Repaired
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000266/LER-1987-002, :on 870409,as Found Containment Integrated Leak Rate Determined to Exceed Allowable Tech Spec Limit.Caused by Packing Failure of One Valve.Valve Replaced & Successfully Tested as Part of Leak Rate Test |
- on 870409,as Found Containment Integrated Leak Rate Determined to Exceed Allowable Tech Spec Limit.Caused by Packing Failure of One Valve.Valve Replaced & Successfully Tested as Part of Leak Rate Test
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000301/LER-1987-003-01, :on 870818,two MSIVs Discovered W/O Dc Control Power Needed to Trip Valves Closed.Caused by Personnel Error.Operation of MSIVs Restored to Complete Clearing Red Tag Series & Dc Power Breaker Closed |
- on 870818,two MSIVs Discovered W/O Dc Control Power Needed to Trip Valves Closed.Caused by Personnel Error.Operation of MSIVs Restored to Complete Clearing Red Tag Series & Dc Power Breaker Closed
| 10 CFR 50.73(a)(2)(v), Loss of Safety Function | | 05000266/LER-1987-003, :on 870424,check Valve for Nitrogen Inlet to Reactor Coolant Drain Tank Vent Header Leak Rate Exceeded Containment Leak Rate Allowed.Caused by Foreign Matl in Nitrogen Piping.Valve Will Be Removed from Svc |
- on 870424,check Valve for Nitrogen Inlet to Reactor Coolant Drain Tank Vent Header Leak Rate Exceeded Containment Leak Rate Allowed.Caused by Foreign Matl in Nitrogen Piping.Valve Will Be Removed from Svc
| 10 CFR 50.73(a)(2)(i) 10 CFR 50.73(a)(2)(1) | | 05000301/LER-1987-004-01, :Degradation of Steam Generator Tubes Noted During Eddy Current Exam Conducted on 871008-22.One Tube Weld Repaired.Remaining Tubes Left as Found Due to Minimal Leakage Observed & Hazards Associated W/Repair |
- Degradation of Steam Generator Tubes Noted During Eddy Current Exam Conducted on 871008-22.One Tube Weld Repaired.Remaining Tubes Left as Found Due to Minimal Leakage Observed & Hazards Associated W/Repair
| 10 CFR 50.72(b)(3)(ii), Degraded or Unanalyzed Condition | | 05000266/LER-1987-004-01, Forwards LER 87-004-01 Detailing Loss of Red Instrument Bus During Replacement of Battery Cell.Encl Delayed Due to Depth of Investigation | Forwards LER 87-004-01 Detailing Loss of Red Instrument Bus During Replacement of Battery Cell.Encl Delayed Due to Depth of Investigation | | | 05000266/LER-1987-005-01, :on 871121,reactor Coolant Pressure Decreased Resulting in Reactor Trip Due to Low Pressurizer Pressure. Caused by Spray Valve Failure.Broken Solder Connection Repaired & Pilot Valve Steam Replaced |
- on 871121,reactor Coolant Pressure Decreased Resulting in Reactor Trip Due to Low Pressurizer Pressure. Caused by Spray Valve Failure.Broken Solder Connection Repaired & Pilot Valve Steam Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000301/LER-1987-005, :on 871120,control Rod C7 Discovered to Be Out of Alignment.Caused by Blown Fuse.Quadrant Flux Tilt Verified & Found Acceptable.Fuse Replaced |
- on 871120,control Rod C7 Discovered to Be Out of Alignment.Caused by Blown Fuse.Quadrant Flux Tilt Verified & Found Acceptable.Fuse Replaced
| 10 CFR 50.73(a)(2)(iv), System Actuation | | 05000301/LER-1987-006, :on 871219,handwheel Gag on Instrument Air Containment Isolation Valve Found to Be Partially Engaged. Caused by Misjusted Valve.Gag Immediately Removed & Valve Tested to Verify Operability |
- on 871219,handwheel Gag on Instrument Air Containment Isolation Valve Found to Be Partially Engaged. Caused by Misjusted Valve.Gag Immediately Removed & Valve Tested to Verify Operability
| 10 CFR 50.73(a)(2)(1) |
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