LER-1981-054, /03L-0:on 810703,flow Indication for Auxiliary Feedwater Pump 3A Failed to Indicate Flow During Monthly Surveillance Test.Caused by Instrument Card in Power Supply Failure,Causing Input to Flow Indicator to Drop to Zero |
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U.S. NUCLEAR REGULATORY COMMISEION LICENSEE EVENT REPORT CONTROL BLOCK / / / / / / / (1)
(PLEASE PRINT OR TYPE ALL REQUIRED INFORMATION)
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LICENSEE CODE LIC2NSE NUMBER LICENSE TYPE CAT
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REP
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U DOCKET NUMBER EVENT DATE REPORT DATE EVENT DESCRIPTION AND PROBABLE CONSEQUENCES (10)
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/ On July 3, 1981 with Unit 1 at 85% power, it was discovered that the flow inlic- /
/0/3/
/ ation for the 3A Auxiliary Feedwater Pump failed to indicate flow during the
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/ monthly surveillance test. The pump discharge flow was verified by a decrease
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/ in main feedwater flow with stable steam generator level.
The health and safety /
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/ of the general public were not affected.
This is contrary to T.S. 3.3.3.6 and
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/ reportable pursuant to T.S. 6.9.1.9.b.
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SYSTEM
CAUSE
CAUSE COMP.
VALVE CODE CODE SUBCODE COMPONENT CODE SUBCODF SUBCODE
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/E/ (12)
/E/ (13) /I/N/S/T/R/U/ (14)
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SEQUENTIAL OCCURRENCE REPORT REVISION LER/R0 EVENT YEAR REPORT NO.
CODE TYPE NO.
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REPORT NUMBER
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ACTION FUTURE EFFECT SHUTDOWN ATTACHMENT NPRD-4 PRIME COMP. COMPONENT TAKEN ACTION ON PLANT METHOD HOURS SUBMITTED FORM SUB. SUPPIIER MANUFACTURER
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/Z/ (20) /Z/ (21) /0/0/0/0/ (22) /Y/ (23)
/N/ (24) /N/ (25) /W/1/2/0/ (26)
CAUSE DESCRIPTION AND CORRECTIVE ACTIONS (27)
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/ An instrument card in the power supply for FT-FW-100C fai!cd causing t he input to/
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/ the flow indicator to drop to 0 volts.
Consequently, the indicator did not show /
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/ a flow. The power supply card was replaced and the flow indication was verified /
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FACILITY METHOD OF STATUS
% POWER OTHER STATUS DISCOVERY DISCOVERY DESCRIPTION (32)
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ACTIVITY CONTENT RELEASED OF RELEASE AMOUNT OF ACTIVITY (35)
LOCATION OF RELEASE (36)
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PERSONNEL EXPOSURES NUMB'IR TYPE DESCRIPTION (39)
/1/7/ /0/0/0/ (37) /Z/ (38)
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PERSONNEL INJURIES NUMBER DESCRIPTION (41)
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LOSS OF OR DAMAGE TO FACILITY (43)
TYPE
DESCRIPTION
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PUBLICITY ISSUED DESCRIPTION (45)
NRC USE ONLY
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NAME OF PREPARER W. R. CARTWRIGHT PHONE (703) 894-3151 8108030118 810722 PDR ADOCK 05000338 S
PDR
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Virginia Electric and Power Company l
North Anna Power Station, Unit 1
Attachment:
Page 1 of 1 Docket No. 50-338 l
Report No. LER 81-054/03L-0
Description of Event
on July 3, 1981 with Unit 1 at 85% power, it was discovered that the flow indication for'the 3A Auxiliary Feedwater Pump failed to indicate flow. The indication failure was discovered while performing the monthly pump surveillance test.
Probable Consequences of Occurrence i
Since the 3A Auxiliary Feedwater Pump flow was verified by a t
decrease in main feedwater flow concurrent with a stable steam generator level and since the other two Auxiliary Feedwater Pumps were also available in the event of a loss of normal feedwater, the
[
health and safety of the general public were not affected.
{
Cause of Event
I The loss of indication was caused by the failure of an instrument card in the power supply for the flow transmitter. The power supply failed low causing the transmitter to indicatt no flow.
Immediate Corrective Action
The 3A Auxiliary Feedwater Pump was immediately verified to be operable by observing a decrease in the main feedwater flow.
The instru-l ment card was replaced and the flow indication was returned to service in less than 7 hours8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br />.
l Scheduled Corrective Action No further corrective action is required.
Actions Taken to Prevent Reccurrence Not further action is required.
Generic Implications There are no generic implications.
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| 05000339/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000339/LER-1981-001-03, /03L-0:on 810101,average RCS Temp Outside Tech Specs on Two Occasions.First Caused by Vol Control Tank Being Overborated;Second by Overcooling Primary.Steam Generator Blowdown Secured,Rods Withdrawn & RCS Diluted | /03L-0:on 810101,average RCS Temp Outside Tech Specs on Two Occasions.First Caused by Vol Control Tank Being Overborated;Second by Overcooling Primary.Steam Generator Blowdown Secured,Rods Withdrawn & RCS Diluted | | | 05000338/LER-1981-001, Forwards LER 81-001/03L-0 | Forwards LER 81-001/03L-0 | | | 05000338/LER-1981-001-03, /03L:on 810318 & 19,nitrogen Supply Tank Pressure for Associated Pressure Operated Relief Valves Dropped Below Min Required to Operate Valves for Low Temp RCS Overpressurization Protection.Caused by Leaks in Tanks | /03L:on 810318 & 19,nitrogen Supply Tank Pressure for Associated Pressure Operated Relief Valves Dropped Below Min Required to Operate Valves for Low Temp RCS Overpressurization Protection.Caused by Leaks in Tanks | | | 05000338/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000338/LER-1981-002-03, /03L-0:on 801231,pressurizer Power Operated Relief Valve Declared Inoperable Because of Low Nitrogen Gas Supply Tank Pressure in 1-GN-TK-1A.Caused by Excessive Usage of Nitrogen to Cycle Relief Valves to Reduce RCS Pressure | /03L-0:on 801231,pressurizer Power Operated Relief Valve Declared Inoperable Because of Low Nitrogen Gas Supply Tank Pressure in 1-GN-TK-1A.Caused by Excessive Usage of Nitrogen to Cycle Relief Valves to Reduce RCS Pressure | | | 05000339/LER-1981-002, Forwards LER 81-002/03L-0 | Forwards LER 81-002/03L-0 | | | 05000339/LER-1981-002-03, /03L-0:on 801230,w/unit in Mode 1,steam Flow Channel III Became Erratic W/O Any Annunciators or Computer Alarms.Cause Unknown.Channel Placed in Trip Condition, Calibr & Returned to Svc | /03L-0:on 801230,w/unit in Mode 1,steam Flow Channel III Became Erratic W/O Any Annunciators or Computer Alarms.Cause Unknown.Channel Placed in Trip Condition, Calibr & Returned to Svc | | | 05000338/LER-1981-003-03, /03L-0:on 810104,loop 3 Reactor Coolant Flow Protection Channel II,F-1435,found Out of Tolerance High. 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