ML19340C500
| ML19340C500 | |
| Person / Time | |
|---|---|
| Site: | La Crosse File:Dairyland Power Cooperative icon.png |
| Issue date: | 11/06/1980 |
| From: | Goodman L DAIRYLAND POWER COOPERATIVE |
| To: | |
| Shared Package | |
| ML19340C499 | List: |
| References | |
| NUDOCS 8011170503 | |
| Download: ML19340C500 (13) | |
Text
A V,'
' OPERATING DATA REPORT DOCKET NO.
50-409 DATE 11-06-80 COMPLETED BY T.S_
Goodman TELEPHONE 60R-6R9-2331 OPERATING STATUS N"I'5
- 1. Unit Name: Lacrosse Soiling Wa&pr Rome &nr 0000, 10/1/80 to 2400, 10/31/80
- 2. Reporting Period:
165
- 3. Licensed Thermal Power (MWt):
65.3
- 4. Nameplate Rating (Gross MWe):
50
- 5. Design Electrical Rating (Net MWe).
50
- 6. Maximum Dependable Capacity (Gross MWe):
48
- 7. Maximum Dependable Capacity (Net MWe)-
- 8. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report.Give Reasons:
- 9. Power Level To which Restricted,if Any (Net MWet:
- 10. Reasons For Restrictions.lf Any:
This Month Yr.-to Date Cumulative 745 7,320 96,435
- 11. Hours in Reporting Period 730.0 6,077.6 63.883.7
- 12. Number Of Hours Reactor Was Critical 0
0 478
- 13. Reactor Reserve Shutdown Hours 717.7 5,813.1 58,817.9
- 14. Hours Generator On.Line 0
0 79
.15. Unit Reserve Shutdown Hours 94,949.0 772,916.4 8.057.696.9
- 16. Gross Thermal Energy Generated (MWH)
- 17. Gross Electrical Energy Generated (MWH, 27,635
_223,820 2,422,952 25,770 208,205 2,240,940
- 18. Net Electrical Energy Generated (MWH) 96.3 79.4 61.0
- 19. Unit Service Factor 96.3 79.4 61.1 20.. Unit Asailability Factor 72.1 59.3 48.4
- 21. Unit Capacity Factor tUsing MDC Net, 69.2 56.9 46.5
- 22. Unit Capacity Factor (Using DER Net) 3.7 13.4 7.1
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Months tty pe. Date,and Duration of Eacht:
Rafnpling nu&ngo. November 9.
1980. 6 weeks j
Estimated Operator Licensinct Examinations, January 12. 1981 2 days l
N/A
- 25. If Shut Down At End Of Report Period. Estimated Date of Startup:
- 26. Units in Test Status t Prior io Commercial Operation s:
Forecast Achiesed IN!TI A L CRITICA LITY INITIA L ELEC IRICITY COMMI RCI % L OPI'R \\ IlON 801117 0 5Q3
AVERAGE DAILY UNIT POWER LEVEL 50-409 DOCKET NO.
LACBWR UNIT DATE 11-06-80 COMPLETED BY L.S.
Goodman TELEPHONE 608-689-2331 October 1980
\\lONTH DAY AVER AGE DAILY POWER LEVEL DAY AV'iRAGE DAILY POWER LEVEL t MWe-Net)
(MWe-Net) 39 37 37 39 is 37 3
39 39 37 4
11.54
- o 37 31 5
9.5 21 e
29 22 26 37 23 35 38 24 37 s
9 38 25 36 10 38 26 37 38 27 36 38 36 l'
- s 13 38 29 35 la 38 30 35 15 38 31 35 l e, 38 INSTRUCTIONS Ou this format. fist the nerage daily umt power levelin MWe-Net for each day in the reporting month. Compute to the ne. ire >t ahole megawatt.
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u 50-409 DOCKETNO.
UNIT SilU1 DOWNS AND POWER REDUC 110NS UNIT NAME LACBWR DATE 11-06-80 COMPLETED BY L.S. Goodman REPORT MONT I Octoher 1980 TELEPHONE 608-689-2331 1
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Cause & Curreceive No -.
Date i
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i 80-10 10-04-80 F
27.3 A
3 N/A CH INSTRU FAILURE OF IB REACTOR FEED PUMP CONTROLLER AMPLIFIER CAUSED PUMP TO Fall HIGH, CAUSING-REACTOR SCRAM ON HIGH WATER LEVEL.
SPARE AMPLIFIER WAS INSTALLED AND TESTED WITH SATIS-FACTORY.'IdOLTS.
CAUSE BELIEVED DUE TO WATER-DETERGENT MIXTURE WHICH SPLASHED ONTO CONTROLLERS AUGUST 22, 1980. REFER TO OUTAGE 80-08, AUGUST 1980 MONTHLY OPERATING DATA REPORT.
80-11 10-21-80 F
0 B
4 N/A HC XXXXX A POWER REDUCTION FROM 81% TO 54% WAS CONDUCTED FOR THE PURPOSE OF REMOVING EACH OF THE TWO TURBINE CONDENSER WATER BOXES TO CLEAN CONDENSER TUBES AND TO REMOVE ACCUMULATED SILT FROM THE WATER BOXES. THE CONDENSER CLEAN-i ING WAS ACCOMPLISHED TO IMPROVE TURBIN : EXHAUST VACUUM AND TEMPERATURE CONDITIONS.
i 2
3 4
F: l urced Reason:
Method:
Exhibit G. Inst uctions S: Scheduled A. Equipment Failure (Explain)
I-Manual for Preparation of Data H Maintenance of Test 2 Manual Scram.
Enity Sheels for Licensee C Refueling 3 Autonutic Ssram.
Esent Repost II.1:R1 File INURI G.
D-Ret;ulatory Restiiction 4 Other (Explain) 0161)
E-Operator Training & laccuse Exanunation F Admimstrative 5
a G. Operational Litur (Explain)
Eshibit I - Same Sousec 08/77) ll-Other IExplain)
N.GRATIVE
SUMMARY
OF OPERATING EXPERIENCE OCTOBER 1980 At the onset of the October 1980 reporting period, power genera-tion was continuing at 85% Reactor Rated Thermal Power (39 MWe-Not.)
This operating level has been scheduled to extend core life to stretch optimum production until the November refueling outage.
On October 4, 1980, at 0732, the reactor shutdown automatically when the IB Reactor Feed Pump controller amplifier failed, causing the pump to increase output speed, resulting in a high water level condition in the reactor vessel.
A spare amplifier and motor were installed and the pump was tested with satisfactory results.
The cause of failure is believed due to the water-detergent mixture which splashed onto the controller on August 22, 1980.
Refer to the August 1980 Monthly Operating Data Report for a discussion of that incident.
The reactor was returned to critical at 2230 on October 4th and the turbine generator was synchronized to the DPC grid at 1050 on October 5th.
Escalation continued until October 7th, when 854 Reactor Rated Thermal Power (38 MWe-Net) was reached.
Power generation continued at this operating level until October 14th, when coastdown to the November refueling outage commenced.
On October 21st, power was reduced from 81% to 54% in order to remove from service each of the two turbine-condenser water boxes to clean condenser tubes and to remove accumulated silt from the water boxes.
The condenser cleaning was accomplished to improve turbine exhaust vacuum and temperature conditions.
On October 23rd, condenser cleaning was completed and power was increased to a peak of 84% Rated Thermal Power, due to xenon decay, and then stabilized at 80% Reactor Rated Thermal Power (37 MWe-Net.)
The slow reactor power coastdown continued, with 77% Reactor Rated Thermal Power (35 MWe-Net) being reached at the end of the October 1980 reporting period.
Significant maintenance items performed during the October 1980
- eporting period are indicated on the attached Instrument and Electrical Maintenance and Mechanical Maintenance listings.
OCTOBER 1980 1.of 3 INSTRUMENT AflD ELECTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUflCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION SECURITY SYSTEM DIESEL NEW INSTALLATION NA TEST UNIT COMPLETED TESTS TESTED OPERATION OF SECURITY POWER DIESEL SECURITY SYSTEM ROOF HATCH CORRECTIVE MR-0022 NA UNKNOWN ROOF HATCH ALARMING ADJUSTED BALANCE ON CIRCUIT BOARD SECURITY SYSTEM ZONE 8 CORRECTIVE MR-0048 NA UNKNOWN 000R SWITCH ADJUSTED BALANCE ON CIRCUIT 000R ALARMING BOARD SECURITY SYSTEM ZONE 20-1 CORRECTIVE MR-0046 NA UNKNOWN MICROWAVE ALARMING ADJUSTED BALANCE ON CIRCUIT I
BOARD SECURITY SYSTEM ZONE 35 CORRECTIVE MR-0054 NA UNKNOWN CONTAINMENT 000R ADJUSTED BALANCE ON CIRCUIT ALARMING BOARD SECURITY SYSTEM ALARM CORRECTIVE MR-0067 NA UNKNOWN CONNECTED SHIELD TO CONNECTED GROUND TO ALARM
' NIT NO. 3 GROUND UNIT N0. 3 SL:URITY SYSTEM CCTV CORRECTIVE MR-0074 NA VIDICON WEAK WASHED OUT PICTURE REPLACED VIDICON TUBE CAMERA NO. 10 SECURITY SYSTEM ZONE 7 CORRECTIVE MR-0078 NA LOOSE D0OR SWITCH INTERMUTENT ALARM TIGHTENED ALARM SWITCH SECURITY SYSTEM CCTV CORRECTIVE MR-0077 NA DIRT & WEBS ON POOR PICTURE CLEANED CAMERA HOUSING AND CAMERA NO. 7 LENS LENS SECURITY SYSTEM CCTV CORRECTIVE MR-0078 NA VIDICON WEAK WASHED OUT PICTURE REPLACED VIDICON TUBE SPARE UNIT SAFETY SYSTEM PREVENTIVE NA TESTS DUE COMPLETED TESTS COMPLETED TECHNICAL SPECIFICA-TION TESTS FOR CH 1, 2, AND WATER LEVEL N0. 3 RADI ATION M0ftlTORING CORRECTIVE MR-0028 NA MOTOR BURNOUT FILTER DRIVE IN0PER. REPLACED FILTER DRIVE MOTOR ATIVE
OCTOBER 2980 2 of 3 IllSTRUMEllT Afl0 ELECTRICAL MAINTENAf4CE
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LER OR flATURE OF OUTAGE MAlfullCTION EQUIPMENT MAlflTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION RADI ATION MONITORING CORRECTIVE MR-3397 NA CONTAMINATION INDPERATIVE CLEANED FLOW METER RADIATIONENViRONMENTAL CORRECTIVE.MR-0071 NA USAGE MONITOR INOPERATIVE REPLACED HOUR METER AND POWER MONITOR SWITCH RADIATION MONITOR CORRECTIVE MR-0093 NA DEFECTIVE CONNECT-SIGNAL IN0 PERATIVE REPLACED CABLE CONNECTOR (CONTAINMENT BUILDING)
OR HYDRAULIC VALVE ACCUMU.
CORRECTIVE MR-0025 NA CONTAMINATED BREAKER POSITION IN-~ AUXILIARY COj-ADJUSTED AND CLEANED.
LATOR 1A CONTACTS DICATION IN0PERADVE FEED PUMP IB CORRECTIVE MR-0009 OUTAGE DEFECTIVL PUMP CONTROL REPLACED CONTROL AMPLIFIER 80-10 AMPLIFIER IN0PERATIVL CONTROL ROD DRIVE NO. 7 CORRECTIVE MR-0030 OUTAGE DEFECTIVE SYNCHR0 PRIMARY POSITION REPLACED UNIT WITH SPARE 80-10 IN0 PERATIVE DIESEL GENERATOR IB START PREVENTIVE MR-0044 LER-80s08 fl0RMAL USAGE BATTERIES NEED REPLACED START BATTERIES CIRCUIT REPLACEMENT FUEL' GRAPPLE TOOL CORRECTIVE NA NORMAL USAGE LAMP IN0 PERATIVE REPLAC.D LAMP AND WIRING MR-0042 & MR-3354 STEAM TO REHEATER FLOW CORRECTIVE MR-0047 NA COMPONENT FAILURE SIGNAL INOPERATIVE RE9 LACED TRANSDUCER AMPLIFIER NUCLEAR INSTRUMENTATION CORRECTIVE MR-0051 NA STRANSDUCER FAILURE RECORDER IN0PERATIVER2 PAIRED STRANDUCER WIRE CH N-5 RECORDER NUCLEAR INSTRUMENTATION PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED TECHNICAL SPECIFICA-CH 5 THRU 9 TION TEST FOR CH 5 THku 9 MAKEUP DEMIN ACID PUMP PREVENTIVE MR-0068 NA M0ISTURE IN MOTOR LOW MEGGER READING CLEANED AND RETESTED MOTOR COMMUNICATIONS SYSTEM CORRECTIVE MR-0081-NA UflKNOWN PHONE SYSTEM ASSITED PHONE COOP WITH INOPERATIVE REPAIR
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OCTOBER 1980 MI:CilAtil('Ai, MA1 NTENANCC LLR OR MALFUflCT10fl flATURE Of OUTAGE mal _ft_T LflAN_C_E_ _ _ _
CORRECTIVE ACTIU_ti_
f.oMr.f R CAUSL RESULT EQUIPME rlT
' 1A AIR COMPRESSOR 3-YEAR P.M.
NA NA NA INSPECTED, REPLACED VANES, MR-0027 BEARINGS, AND MECHANICAL SEALS EAST AIR CONDITIONER IN CORRECTIVE m 0041 NA TURNED IN OUTER OVERHEATED BEARING CHANGED OUT BEARING AND REACTOR BUILDING RACE CAUSING IT TO FAIL PILLOW BLOCK LOWER CRD NO. FRAME 30, CORRECTIVE OUTAGE BAD TRANSMITTER FALSE POSITION PERFORMED PREVENTIVE
!POSITIONNO.7 MR-0030 & MR-0039 80-10 INDICATOR MAINTENANCE (P.M.) CHECKS i
. AND STORED FOR SPARE OFFGAS' SYSTEM CORRECTIVE NA METER PLUGGED UP COULD NOT READ FLOW ADD P0TS TO CATCH FC-55-80-3 PARTICULATES FROM G0ING TIROUGH METER l
REPLACED DIAPHRAGM AND WASTE WATER CORRECTIVE NA RUPTURED DIAPliRAGM VALVE LEAKED THROUGF MR-0085 STEM PIN j
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Pg. l'of 2 i
REFUELING INFORMATION REQUEST 1.
Name of Facility La Crosse Boiling Water Reactor (LACBWR) 2.
Scheduled Date for Next Refueling Shutdown The tentatively scheduled date for the next refueling shutdown (EOC-VI) is November 9, 1980.
3.
Scheduled Date for Restart Following Refueling The tentatively scheduled date for subsequent reactor startup is December 13, 1980.
4.
Will Refueling or Resumption of Ooeration Thereafter Require a Technical Specification Change or Other License Amendment?
If answer is yes, what, in general, will these be?
If answer is no, has the reload fuel design and core configura-tion been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Ref. 10 CFR Section 50.59)?
If no such review has taken place, when is it scheduled?
No Technical Specification Change or license amendment will be needed for refueling or subsequent resumption of operation.
The Safety Review Committee's 50.59 review of the reload fuel design and core configuration will be conducted prior to the commencement of refueling.
5.
Scheduled Date(s) for Submitting Proposed Licensing Action and Supporting Information N/A 6.
Important Licensing Considerations Associated with Refueling, e.g.,
New or Different Fuel Design or Supplies, Unreviewed Design or Performance Analysis Methods, Sionificant Chances in Fuel Design, New Operating Procedures None 7.
The Number of Fuel Assemblies (a) in the Core and (b) in the Spent Fuel Pool Core Loading:
72 Fuel Assemblies Spent Fuel Storage Pool Loading:
133 Irradiated Fuel Assemblies i
.~
Pg, 2 of g REFUELING INFORMATION REOUEST - (Cont'd) 8.
The Present Licensed Spent Fuel Pool Storage Capacity and the Size of any Increase in Licensed Storage Capacity that has been Requested or so Planned, in Number of Fuel Assemblies.
440 Fuel Assemblies 9.
The Projected Date of the Last Refuelina that can be Discharged to the Spent Fuel Pool Assuming the Present Licensed Capacity.
1990 t
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