ML20024F056

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Monthly Operating Rept for Jul 1983
ML20024F056
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 08/10/1983
From: Goodman L, Linder F
DAIRYLAND POWER COOPERATIVE
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
LAC-9249, NUDOCS 8309080162
Download: ML20024F056 (8)


Text

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i OPERATING DATA REPORT j

DOCKET NO. 50-409 DATE 08/10/83 COMPLETED BY L. S. GOODMAN TELEPHONE 608-689-2331 OPERATING STATUS I

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1. Unit Name:

La Crosse Boiling Water Reactor l NOTES:

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2. Reporting Period: 0001, 07-01-83 to 2400, 07-31-83 l

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3. Licensed Thermal Power (MW ):

165 l

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4. Nameplate Rating (Gross MW ):

65.3 l

l S. Design Electrical Rating (eNet MW ):

50 l

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6. Maximum Dependable Capacity (Gross MW ):

50 l

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7. Maximum Dependable Capacity (Net MW )e e:

48 l

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8. If Changes Occur in Capacity Ratings (Items 3 Through 7) Since Last Report, Give Reasons:
9. Power Level To Which Restricted, If Any (Net MWe)*
10. Reasons for Restrictions, If Any:

This Month R.-to-Date Cumulative

11. Hours In Reporting Period 744 5,087 120,506
12. Number Of Hours Reactor Was Critical 352.9 4,234.7 79,609.8
13. Reactor Reserve Shutdown Hours 0

0 478

14. Hours Generator On-Line 345.6 4,076.0 73,679.4
15. Unit Reserve Shutdown Hours 0

0 79

16. Gross Thermal Energy Generated (MWH) 50,612.9 597,776.4 10,120,319.5
17. Gross Electrical Energy Generated (MWH) 14,207 171,839 3,012,027
18. Net Electrical Energy Generated (MWH) 13,003 160,503 2,786,471
19. Unit Service Factor 46.5 80.1 61.1
20. Unit Availability Factor 46.5 80.1 61.2
21. Unit Capacity Factor (Using MDC Net) 36.4 65.7 48.2
22. Unit Capacity Factor (Using DER Net) 35.0 63.1 -

46.3

23. Unit Forced Outage Rate 53.5 14.9 8.3
24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Refueling, October 1983, 6-8 Weeks

25. If Shut Down At End Of Report Period, Estimated Date of Startup:

August 13, 1983

26. Units In Test Status (Prior to Commercial Operation):

Forecast Achieved INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCIAL OPERATION WP-6.8 8309080162 030810 DRADOCK05000g MN

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 UNIT LACBWR

'DATE 08/10/83 COMPLETED BY L. S. Goodman TELEPHONE 608-689-2331 MONTH JULY, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 41 17 0

2 41 18 0

3 41 19 0

4 41 20 0

5 41 21 0

6 41 22 0

7 41 23 0

8 41 24 0

9 24 25 0

10 5

26 0

11 24 27 0

12 34 28 0

13 39 29 0

14 40 30 0

15 40 31 0

16 19 1

INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

WP-6.8

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UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO.

50-409 UNIT NAME LACBWR DATE 08/10/83 REPORT MONTH JULY, 1983 COMPLETED BY L. S. GOODMAN TELEPHONE 608-689-2331 l

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l 2lShuttinggownl l Typel l Duration l l Systgm l Compongnt l Event Action to l

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1 Date I (Hours) l Reason l Reactor l Report # l Code l

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Prevent Recurrence i

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l 83-07 1 07/09/83 i F

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SA l PENETR l Reactor shutdown due to l

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1 83-08 l 07/16/83 l F

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83-07 l

WB l PIPEXX l During operation, seal injecti l

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1 Forced Circulation Pump SI I

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l l reactor scrammed. Approxi-l l

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l mately 15,000 gallons of SI l

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1 Gaskets replaced. Changes tol l

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4 F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Automatic Scram Event Report (LER) File D-Regulatory Restriction 4-Other (Explain)

(NUREG-0161)

E-Operator Training & License Examination F-Administrative 5

G-Operational Error (Explain)

Exhibit 1 - Same Source H-Other (Explain)

JULY, 1983 SHEET 1 0F 3 INSTRUMENT AND ELECTRICAL MAINTENANCE l

4 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION SECURITY MICROWAVE 20-6 CORRECTIVE NA UNKNOWN ALARM REBALANCED AMPLIFIER MR-0456 SECURITY "E" FIELD CORRECTIVE NA UNKNOWN ALARM REBALANCED AMPLIFIER ZONE 19-4 M1-0464 SECURITY "E" FIELD 19-6 CORRECTIVE NA UNKNOWN ALARM REBALANCED AMPLIFIER j

MR-0465 i

SECURITY MICROWAVE 20-4 NO MAINT.

NA EN WORKING ALARM NONE MR-0478 IN AREA SECURITY COMPUTER CORRECTIVE NA COMPUTER COMPUTER DOWN INSTALLED CROSS CABLES i

MR-0437 MALFUNCTION TO TSC COMPUTER SECURITY ACCESS ALARM CORRECTIVE NA NOT IN PROGRAM NO ACCESS ALARM REPROGRAMMED COMPUTER 2

l PT 36 MR-0490 i

SECURITY "E" FIELD 19-6 NO MAINT.

OUTAGE BIRDS IN AREA ALARM REMOVED BIRDS MR-0501 83-08 1

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.0UTAGE UNKNOWN ALARM BALANCED AMPLIFIER MR-0521 83-08 l

SECURITY "E" FIELD 19-4 CORRECTIVE OUTAGE UNKNOWN ALARM BALANCED AMPLIFIER i

MR-0527 83-08 i

SECURITY ALARM AP22 CORRECTIVE OUTAGE LOOSE WIRE NO ALARM TIGHTENED LOOSE WIRE MR-0530 83-08 l

SAFETY SYSTEM CH 1, 2 &

PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED TESTS l

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NUCLEAR CH N-5 THROUGH N-9 PREVENTIVE OUTAGE TEST DUE COMPLETED TESTS COMPLETED TESTS i

83-07 I

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JULY, 1983 SHEET 2 0F 3 INSTRUMENT AND ELECTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION CALIBRATION NH3 MONITOR PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED TESTS MR-0477 HEATING BOILER INDICATORS FACILITY CHANGE OUTAGE FC 73-83-5 COMPLETED INSTALLED LAMPS ON LEVEL 73-83-5 83-08 INSTALLATION CONTROLS MR-0486 CONTROL ROOM CONTROLLERS PREVENTIVE OUTAGE DUST & NICOTINE CLEANED SWITCHES CLEANED SWITCHES AND MR-0512 83-08 CONTAMINATION UNITS TURB. VIBRATION RECORDER CORRECTIVE NA USAGE MISPRINT ADJUSTED ADVANCE MR-0462 MECHANISM WASTE WATER TANKS CORRECTIVE OUTAGE DIRT - MUD NO LEVEL ALARM FLUSHED LEVEL CHAMBER MR-0093, 0227 83-08 NUCLEAR CH N-5, N-6 CORRECTIVE OUTAGE UNKNOWN TRIP ALARM IN REBALANCED CONTROL UNIT MR-0478 83-07 NUCLEAR CH N-5 RECORDER CORRECTIVE OUTAGE STRING OFF NO RECORDING REPLACED STRING ON PULLEY MR-0488 83-08 PULLEY HIGH PRESSURE SERVICE WATER CORRECTIVE OUTAGE USAGE MALFUNCTION ON REPLACED BEARINGS AND ELECTRIC PUMP MOTOR MR-0480 83-08 STARTS CONTACTOR CONTACTS 18 FORCED CIRCULATION PUMP CORRECTIVE OUTAGE WATER / STEAM NO OUTPUT REPLACED TEMP ALARM UNIT (FCP) TEMP ALARM UNIT MR-0509 83-08 LEAKAGE MAKE-UP DEMINERALIZERS CORRECTIVE OUTAGE USAGE VALVE IN0PERABLE REPLACED VALVE SEAT AND MR-0515 83-08 PLUNGER 1B SEAL INJECT SUPPLY VALVE CORRECTIVE OUTAGE VIBRATION STOPPED VALVE READJUSTED CONTROL AND MR-0513 83-08 OPERATION SEALED SETTING LER 83-07 SEAL INJECT AIR PRESSURE CORRECTIVE OUTAGE USAGE GAUGE IN0PERABLE REPLACED GAUGE GAUGE MR-0404 83-08

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JULY, 1983 SHEET 3 0F 3 INSTRUMENT AND ELECTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION REACTOR SUMP CONTROL CORRECTIVE OUTAGE USAGE MALFUNCTION ON REPLACED ALTERNATOR MR-0517 83-08 SWITCH CONTROL LER 83-07 FCP 1A BEARING CORRECTIVE OUTAGE UNKNOWN THERM 0 COUPLE OPEN REPLACED THERM 0 COUPLE THERMOCOUPLE MR-0455 83-08 EAST TURBINE SUMP CONTROL CORRECTIVE OUTAGE OIL, SCUM LEVEL CONTROL CLEANED SUMP AND CONTROL MR-0523 83-08 INOPERABLE PROBES GENERATOR EXHAUSTER MOTOR CORRECTIVE OUTAGE USAGE NOISE IN BEARING REPLACED MOTOR BEARINGS MR-0526 83-08 SEAL INJECT LEVEL SWITCH CORRECITVE OUTAGE UNKNOWN INDICATOR UNPLUGGED SENSING LINE INDICATOR MR-0536 83-08 IN0 PERATIVE MAKEUP DEMIN. LEVEL CORRECTIVE OUTAGE ACID DISSOLVED PROBE T00 SHORT REPLACED LEVEL PROBES PROPES MR-0533 83-08 PROBE e

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.O NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE JULY 1983 At the onset of the July 1983 reporting period, power generation was continuing at 93% Reactor Rated Thermal Power (41 MWe-Net).

On July 9, a manual reactor shutdown was conducted due to failure of a Type B leakage test on the personnel airlock. This event was discussed in Reportable Occurrence No. 83-05. The reactor was taken critical at 0445 on July 10, but a spurious spike on Nuclear Instrumentation Ch. 5 resulted in an automatic shutdown at 0506. The reactor was returned to critical at 0941 on July 10 and the turbine-generator was synchronized to the DPC grid at 1631.

Power escalation continued until July 15, when 93% power was cchieved.

At 1123 on July 16, the reactor automatically shutdown when the Forced Circulation Pumps tripped due to a gaskct failure in the Seal Inject System. Refer to R0 83-07 for a discussion of the event. The reactor remained shutdown for the rest of the month.

Type B leakage tests were conducted on the personnel and emergency airlocks during the month of July. As discussed above, the personnel airlock did not pass the initial test. The as-left leakage rates of the airlocks were as follows:

Personnel Ai rl ock.............. 0.188 SCFH Emergency Ai rl ock.............. 0.389 SCFH l

Significant Instrument and Electrical Department maintenance items performed during the July 1983 reporting period are included on the attached l

Instrument and Electrical Maintenance listing. Significant Mechanical l

Maintenance items performed during the July 1983 reporting period will be j

submitted in a supplement to this report.

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/ 0lDA/RYLAND h

[k COOPERAT/VE e.o. Box 817 26is EAST AV SOUTH = LA CROSSE. WISCONSIN S4601 (608) 788-4000 August 10, 1983 In reply, please refer to LAC-9249 DOCKET NO. 50-409 Office of Management Information and Program Control U. S. Nuclear Regulatory Commission Washington, D. C.

20555

SUBJECT:

DAIRYLAND POWER COOPERATIVE LA CROSSE BOILING WATER REACTOR (LACBWR)

PROVISIONAL OPERATING LICENSE NO. DPR-45 MONTHLY OPERATING DATA REPORT FOR JULY,1983

Reference:

(1) NRC Letter, Reid to Madgett, dated September 19, 1977.

(2) NRC Letter, Reid to Madgett, dated December 29, 1977.

Gentlemen:

In accordance with instructions contained in Reference (1) and Technical Specification Amendments contained in Reference (2), we are submitting information concerning operability and availability of the La Crosse Boiling Water Reactor (LACBWR) for the Month of July,1983.

Please contact us if there are any questions concerning this report.

Very truly yours, DAIRYLAND POWER COOPERATIVE 4,gyJf sV c-/ Frank Linder, General Manager FL:LSG:eme cc:

J. G. Keppler, Dir., NRC-DRO III NRC Resident Inspector

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l 55, WP-6.8

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