ML20062E791
| ML20062E791 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 12/06/1978 |
| From: | Papworth L DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML20062E783 | List: |
| References | |
| NUDOCS 7812120132 | |
| Download: ML20062E791 (10) | |
Text
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OPERATING DATA REPORT DOCKETNO 50-409 D \\IE 12-06-78 CO\\lPLETED BY 7 E Pnpworth TELEPHONE ec Aco-2331 4
OPER \\ TING STATUS I
La Crosse Boiling k'ater Reactor Notes i
- 1. Unit Name:
- 2. Reporting Period: 0000 78-01-11 to 2400 78-30-11 3.1.icenwd Thennal Power 1%1h ti: 165
- 4. Nameplate Rating (Grow %lhes:
65.3
- 5. Design Electrical Rating 4 Net \\lhe s:
50
- 6. Stasimum Dependable Capacity (Grow 3 thel: 50 7.\\lasimum Dependable Capaeir> INet 3then.
48
- 5. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since La t Reg ort. Gise Reason -
l.
- 9. Power Lesel To hhich Re trieted.lf An> tNet \\lhes.
l.8 ';et 3G*e
- 10. Reasons for Restrictions. lf Any: Self-ir. posed restriction due to Nuclear Instrumentation noise at hicher power levels (voids in steam separators).
This alonth Yr.to.Date Cumultise
- 11. Hours in Reporting Period 720 C016 79.611
- 12. Number Of Hours Reactor has Critical 395.6 5256.7 50,435.2
- 13. Reactor Rewne Shutdown Hours 0
0 479
- 14. Hours Generator On-Line 270.1 46S3.8 45,974.1
- 15. Unit Resene Shutdow n Hour <
0 0
79
- 16. Grow Thermal Energy Generated t \\lh Ha 21.20^
592.062 6.475.362 l-Gross Electrical Energy Generated tYkH 5 670 171_201 1.oA4.345
- 15. Net Electrical Energ> Generated t\\lhHe 4.750 157.625 1.CI5.205 14 Unit Senice Factor 37.5 5
,4 57.2
- 20. Unit Asailability Factor 37.5 33.4 57.5
- 21. Unit Capacits Factor tC ing stDC Net, 13.7 41.0 47.5
- 22. Unit Capacity Factor iL mg DER Net, 13.2 39.3 45.6
- 23. Uni Forced Outage Rate 30.0 17.8 5.6
- 24. Shutdowns Scheduled Oser Nest 6 \\1onth,i T pe. Date.and Duration nl E. h 3
Refueling shutdown, February 10, 1979, tentative shutdoun date, 8-veek duratien.
- 25 It Shui linwn \\t End Of Report Pennd. i. nnated 18 ate ut startup
'!A 26 1 me, in f est status (Pneer to ( ummeraal Operatnini I nrec.ist
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50-409 UNII N AME _.LACBW D OE 12-06-78 kl POR I MONigg _NOVEMBEP 1978
( OMPLEII D sy L.G.Papworth TELIPilONE 608-689-2331_
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NA CB PitMPXX Containnent Building Integrated Leak from Rate Testing (Type A) continued into oc t ein r Novem er 1978. Outage 78-14 was in-1978 itiated for the major reason of re-i pairing Forced Circulation Pun:p 1A Fluid Coupling. This repair was com-pleted in October.
D-Is 18-11-17 F
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3 NA 1A INSTRU A low flow spike indication on Forced Circulation'. cop I A caused a shutdewn based on a power to flow mismatch in P/F Channel 1.
The two P/L channels operate in a 1-of-2 logic. The Forc-ed Circulation Loop flow transmitters and square root. converters associated with P/F Channel No. I were checked and Technical Specification tests were performed with no abnormalities ob-served. No equipment was replaced.
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50-409 LACBk'R
\\tONTil NO\\' EMBER 1978 D\\Y
.tVER \\GE D \\lLY POhER LE\\ El DG WER \\GE D \\lLY POhER LEVEL gps,,3,,,
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uaSTRUMfMT AND ELECTRICAL MAINTE. <CE NOVEMBER 1978 LER OR NATUof 0F OUTAGE MALTUNCT10ft l
E0UIPMENT 4
MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTIO!;
1.1.AE RNIE TEST - IlUMIDI1Y Corrective Outage Adjustment off.
Incorrect readout.
Adjusted zero and span;-
F I CORDI:R MR 2255 78-14 replaced amplifier.
2 StT!. EAR INS 18UMI:NTATI ON Corrective Outage Defective tubes.
Reading low.
Replaced tubes.
5.'
MR 2266 78-14
'itTIL\\R INSTRUMEN1 ATION Corrective Outage Defective Heading low.
Replaced power supp1v N-6 MR 2308 78-15 capacitor capacitor.
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e SI:EURITY SYSIEM ZONE 5 Corrective Outage Improper align-No alarm.
Realigned unit.
MR,2257 78-14 ment.
'I'.URITY SETE:t ZONE 9
+orrective NA Defective unit.
No alarm reser.
Replaced unit with sparc.
Mk 2305 Sect' PITY SYS1EM ZONE 5 Corrective NA Defective unit.
Periodic alarm.
Adjusted line current.
MR 2327 Dl211N. L!ATER Corrective Outage Opened coil.
Valve inoperative.
Replaced solenoid coll.
MR 2277 78-14 nefPo'iENT r001.ING WATF.R Corrective Outage Defective bearing.
Rough operation.
Replaced motor bearing.
II; MR 2274 78-14 i
lef t:SEl. I'll:E IT!!P IB Corrective NA Thermostat inoper-I.o Temperat ure Replaced burned wire on MR 2300 able.
Alarm unit.
FITDI!ATER IIEATER #3 Corrective NA Valve 1.cak I.evel too high.
Adjusted valve controller.
MR 2295 Through
If4STRUMENT AND ELECTRICAL MAINTENA.. E NOVEMBER 1978 LER OR NATURE OF-OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION CIRCULATION SYSTEM Corrective
- Ou'tage Calibration Re-Test flows.
Calibrated 1A and IB MR 2310 78-15 quest.
Flow System NUCLEAR INST. N-6 Preventive Outage Clean and adjust Check proper oper-Cleaned and checked MR 2311 78-16 request.
ation.
switch.
SEAL INJECTION SYSTEM Corrective Outage Defective trans-Loss of flow.
Replaced transmitter MR 2316 78-16
- mitter, bellows.
FEEDWATER FLASli TANK Corrective Outage Loose valve feed-Valve not closed.
TJghtened connection.
MR,2319 78-16 back connection.
SEAL INJECTION SYSTEM Corrective Outage Defective power Low reading.
Replaced power supply.
SUPPLY MR 2322 76-16 supply.
DIESEL FIRE PUMPS lA-1B Preventive NA Improper cooling.
Engine overheat.
Replaced valve and control FC-78-04 unit.
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MCCIIANICAL MAI?!TENA?!C; NOVDillER 1978 1.ER OR flMURE OF OUTAGE MALFUNCTI0fl
~
_0Ul FME!1T MAlfiTE NAtlCE t4 UMBER CAUSE RESULT CORRECTIVE ACTIG f
' F '. Pl ?!!'
Correct.ive Outage Normal Wear I.eakage past Mech-Replaced seal.
MR 2040 78-14 anical shaft seal.
i 41; Pl Mi' Preventive Outage MR 2260 78-14 NA NA Replaced mechanical seal.
' o I ti lioUS!. NORTil INTAKE Preventive Outage NA NA Installed "stop-logs",
- t. 3 78-14 pumped out bay and inspected st ructure an<i pumps and v ere found to be OK.
AIR E. LECTOR AFTER Corrective Outage Pressure and temp-Tube-end leak.
Rerolled tube end.
Ci clit.N S Elt Mn 2312 78-15 erature cycles.
"A" FCp Corrective Outage Uncertain Excessiva seal wear Rebuilt seal.
MR 2318 78-16 and leakage.
I MI.RGl:Nf Y * ! RI.OCE INNER Corrective Outage Set screw loosened Cam roller fell out Reinstalled cam roller.
laMK MR 2313 78-16 up, of position.
Door lwould not operate e
- properly, i
'l AUXil.IARY 011 Pt:Mi' Corrective Outage Normal wear.
Reduced pumping
{ Adjusted internal clear-MR 2286 78-14 capacity.
iances.
litLl LNCY AIRLOCK OUTER Corrective R0-78-12 IIall and seats Valve leaked during Installed new ball and I leESTI'RE EQUALIZING BALL MR 2326 scored by foreign IType "B" pressure
- seats.
VALVE particles.
{testofairlock.
f rt:RI:lNE CONDENSER COOLING Corrective Outage
' Sight glass broke Circulating water iReplaced broken sight glass.
WATl.R lt0NITOR l'I.0tatETER MR 2321
. 78-16 while adjusting leak.
l flow.
I.19UID WASTI. AND SERVICE Corrective Outage Debris stuck in Flowmeter would not Cleaned flowmeter.
'..VI 1 1: ;10N! LOR I1.OWtETER MR 2320 78-16 flowmeter.
{functionproperly.
lil.ATI NG TENI TO REACTOR Corrective Outage (Worndiseand
{ Valve leakage.
Replaced disc and seats, l l~ l l.lil NG I Sol.ATIoS VA!.VE MR 2246 78-14 seats.
i t
Corrective l0utage f in jector Cracked Fuel Oil I.eak
!Heplacedinlector.
I ia 51 RATol:
l MR 2220 178-14 l
MECIIANICAL MAINTENANCE NOVEMBER'1978 LER OR NATURE OF OUTAGE MALFUNCTI0ff 2
EQUIPMENT MAltlTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION N2 CilARGING BOOSTER PUMP Corrective Outage Worn components.
Loss of pump head.
Overhauled pump.
MR 2275 78-14
'IB CONTROL ROD DRIVE Corrective Outage Installed internal o-rings.
!!YDRAULIC CilARCING PUMP MR 2281 78-14 Worn seal.
Shaft seal leaks.
shaft seal and gaskets.
l
i NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE NOVEMBER 1978 At the onset of the November reporting period, periodic primary Reactor Containment Integrated Leak Rate Testing (Type A) was in effect.
This testing was satisfactorily completed on November 5, 1978.
Post ILRT valve line-up restoration and reactor plant startup preparations were completed on November 8 and the reactor was taken critical at 2030 hours0.0235 days <br />0.564 hours <br />0.00336 weeks <br />7.72415e-4 months <br /> that day.
Power escalation continued and the plant was connected to the DPC grid at 1745 hours0.0202 days <br />0.485 hours <br />0.00289 weeks <br />6.639725e-4 months <br /> on November 10.
Power escalation continued until 1900 hours0.022 days <br />0.528 hours <br />0.00314 weeks <br />7.2295e-4 months <br /> on November 11, 1978, when a power reduction from 40% power (13 MWe-net) was initiated due to an indication of a higher than normal off-gas activity level.
The high level indication was determined to be caused by moisture carry-over from a leaking tube in the air ejector after condenser.
The after condenser was repaired during a subsequent plant shutdown.
At no time were off-gas activity limits exceeded.
Power eacalation was initiated from 20.6% power (8 MWe-net) on November 12, 1978 and continued until 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br /> on November 17, 1978, when at a power level of 62.2% power (28 MWe-net), a reactor scram occurred.
A low flow spike indication on Forced Circulation Loop 1A caused indication of a power-to-flow mismatch in power-flow safety channel No. 1, which in turn initiated the reactor scram signal.
The Forced Circulation Loop flow transmitters and square root converters associated with P/F Channel No. 1 were checked and technical specification testing was performed with no abnormalities observed.
No equipment was replaced.
The reactor was subsequently taken critical at 0920 hours0.0106 days <br />0.256 hours <br />0.00152 weeks <br />3.5006e-4 months <br /> on November 19, 1978.
Reactor heatup continued until 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br /> en November 20, 1978 when excessive seal wear was indicated on Forced Circulation Pump 1A and the 1A pump was secured with the intention of orderly plant shutdown.
A low flow indication prompted an auto-i matic reactor scram at that time.
The upper face seal was found to l
be badly worn upon inspection and was replaced.
The exact cause of the abnormal seal wear and degradation is being investigated.
A reactor startup was conducted on November 24, 1978 with the reactor taken critical at 2021 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.689905e-4 months <br />.
The plant was connected to the DPC grid at 2202 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.37861e-4 months <br /> on November 26, 1978.
Reactor escalation was con-tinuing at the end of the November reporting period at a level of 59% power.
Significant maintenance items performed during the reporting period are indicated on attached Instrument and Electrical Maintenance and Mechanica3 Maintenance listings.
. +*
M7tRRATIVE
SUMMARY
OF OPERATING EXPERIENCE - (Cont ' d)
The maximum power level at which the reactor was operated during November 1978 was 62.2% of rated reactor power (28 MWe-not).
The off-gas activity levels, as measured at the 150 ft3 holdup tank effluent monitor (prior to entry into the augmented off gas holdup system) did not exceed 501 curies per day (this at 59% power) during November, 1978, and the adpNa activity in the primary coolant did not exceed 1.06 x 10-6 uCi/gm during the reporting period.
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