ML20050F774

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Monthly Operating Rept for May 1981
ML20050F774
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 06/03/1981
From: Goodman L
DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20050F771 List:
References
NUDOCS 8204130378
Download: ML20050F774 (8)
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Text

.

OPERATLiG DATA REPORT

~

50-409 DOCKET NO.

DATE 06-03-81 COMPLETED 11Y L.S. GOODMAN TELEPl!ONE 6np 6Ro 9331 OPERATING STATUS N

1. Unit Name: LA CROSSE B0ILING WATER REACTOR
2. Reporting Period: 0001, 05-01-81 TO 2400. 05-31-81 165
3. Licensed Thermal Power (MWI):

65.3

4. Nameplate Rating (Gross Mile):

50

5. Design Electrical Rating (Net MWe):

50

.2

6. Maximum Dependable Capacity (Gross MWe):

48

7. Maximum Dependable Capacity (Net MWe):
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:
9. Power Lesel To which Restricted.If Any (Net MWe):
10. Reasons For Restrictions.lf Any:

This Month Yr to Date Cumulative I1. Ilours In Reporting Period 744 3623 1 01;5??

12. Number Of Hours Reactor Was Critical 528.8 2732.3 66.829.3
13. Reactor Reserve Shutdown flours 0

0 47R 522.7 2552.0 61.583.3

14. Ilours Generator On-Line 0

0 79

15. Unit Resene Shutdown Hours
16. Cross Thermal Energy Generated (MWH) 75,691.0 354.918.5 8.439.255.9
17. Gross Electrical Energy Generated (MWH) 21,900

_. 102.294 5.532.929 20,395 95,038 2.342.318

18. Net Electrical Energy Generated (MWH) 70.3 70.4 60.7
19. Unit Service Factor
20. Unit Availability Factor 70.3 70.4 60.7 57.1 54.7 48.1
21. Unit Capacity Factor (Using MDC Net) 54.8 52,5 46.1
22. Unit Capacity Factor (Using DER Net) 2.3 4.0 7.0 23._ Unit Forced Outage Rate
24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Eacht:

NONr

25. If Shut Down At End Of Report Period. Estimated Date of Startup: JUNE 12. 1981
26. Units In Test Status (Prior to Commercial Operation):

Forecast Achiesed INITI A L CRITICA LITY INITIAL ELECTRICITY COMM ERCI A L OPER ATION 8204130378 810609 08/77 )

DR ADOCK 05000409 PDR

O AVERAGE DAILY UNIT POWER LEVEL 50-409 DOCKET NO.

LACBWR 3 37 06-04-81 DATE CONIPLETED BY L.S.G0ODMAN TELEPilONE 608-689-2331 MONDI MAY 1981 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL W

(MWe-Net)

(MWe-Net) 4 i

40 37 2

40 i8 39 3

40 19 39 4

_ _4n 20 39 s

40 2:

39 6

39 22 39 7

17 23 6

8 22 24 0

9 35 25 0

to 40 26 0

il 40 27

.o 12 42 28 0

13 43 29 0

14 44 30

'O is 4R 3

0 to 45 INSTRUCIIONS On this format, Int the aserage daily unit power levelin MWe Net for each day in the reportmg month. Compute to ite nearest whole nepwati.

(9/77 )

o -

UNITSilU1 DOWNS AND POWER REDUC 110NS DOCKET NO. 50-409 UNIT N AME LACBWR DATE nG na 91 MAY 1981 COMPLETED BY L.S. GOODMAN REPORT MONTil TELEPHONE 608-689-2331

!?

3 Ek Licensec g-r, h*o Cause & Correctise N".

Date i

3?

4 2sE Event u?

5 '8 Action to

$E E

jgg Report r cE0

}L Present Recurrence 6

81-07 05-07-81 F

12.0 G

3 NA IA CKTBRK OPERATOR DID NOT RESET SCRAM PRIOR TO RETURNING SCRAM TEST SWITCH T0

" NORMAL" DURING POWER-FLOW TECHNICAL SPECIFICATION TEST.

PROCEDURE FOR-MAT WAS REVISED TO MORE CLEARLY DELINERATE EACH STEP.

81-08 05-23-81 S

209.3 B

1 NA ZZ ZZZZZZ SCHEDULED OUTAGE FOR FUEL RECEIPT AND MAINTENANCE. ACTIVITIES INCLUDED INSTALLATION OF SEISMIC RESTRAINTS AND PIPE HANGERS, TMI MODIFICATIONS, FILTERING OF TURBINE OIL, AND WORK ON 1A FORCED CIRCULATION PUMP SEAL.

I 2

3 4

i: Forced Reason:

Method:

Eslubit G Instructions 3

S: Scheduled A. Equipment Failure (Explain) 1-Manual for Preparation of Data

'i B. Maintenance or Test 2-Manual Scram.

Entry Sheets for 1.icensee C Refueling 3-Autonntic Scram.

Eve.it Report i1.1 R1 File tnt'RI.G-D. Regulatory Restriction 4-Other (Explain) 01611 E-Operator Training & license lixamination F Administrative 5

G-Operational trror (E xplain)

Eshibit 1 - Same Source 19/77)

Il-Ot her (Esplain)

NARRATIVE

SUMMARY

OF OPERIsTING EXPERIENCE J

MAY 1981 At the onset of the May 1981 reporting period, power generation was at 88% Reactor Rated Thermal Power (4 0 MWe-Net).

This power level had been scheduled to optimize power production by extend-ing the period between refueling outages.

On May 7, 1981, the reactor automatically shut down at 1013 when the reactor operator returned the scram test switch to " NORMAL" prior to resetting the scram during the monthly Safety System Channel No. 1 Power-Flow Technical Specification Test.

The reactor was returned to critical at 1615 on May 7, and the turbine-generator resynchronized to the DPC grid at 2215 that day.

Power escalation continued until May 14, when 98% Reactor Rated Thermal Power (45 MWe-Net) was achieved, in order to conduct the annual Mid-Continent Area Power Pool (MAPP) Rating Test.

Oper-ation continued at this power level until May 17.

On May 17, power was reduced to 85% Reactor Rated Thermal Power (38 MWe-Net) due to increased vibration of the 1B Forced Circul-ation Pump at the higher pouer level.

Vibration decreased, so power was re-escalated to 88% Reactor Rated Thermal Power (39 MWE-Net) on May 18.

Power generation continued at this level until May 23 when de-escalation commenced for the scheduled outage.

The turbine-generator was removed from the DPC grid at 0645 on May 23.

Outage activities included receipt of irradiated fuel from Morris, Illinois, installation of pipe hangers and ceismic restraints, TMI modifications, flushing and filtering of the turbine oil system, and work on the 1A Forced Circulation Pump seal.

Significant maintenance items performed during May 1981 are indi-cated on the attached Mechanical Maintenance and Instrument and Electrical Maintenance listings.

MECIIAMICAL MAINTENANCE MAY 1981 i

I LER OR flATURE OF OUTAGE tigfU!iCT10ft EQUIPMEf1T l'AlfiTEtiAf4CE fMBER CAUSE RESULT CORRECTIVE ACT104 REACTOR PLANT BATTERY FABRICATION NA NA NA FABRICATED RESTRAINTS RACK RESTRAINTS (NES W1814 FOR BATTERIES TO KEEP DWG, ISK5101- 063-2)

THEM FROM MOVING IN 1

CASE OF AN EARTHQUAKE.

N2 BOTTLE RACK RE-FABRICATION NA NA NA FABRICATED RESTRAINTS STRAINTS (NES DWG.

W1814 FOR N2 BOTTLES TO KEEP

  1. SK5101-063-3)

FROM MOVING IN CASE OF AN EARTHQUAKE.

ALTERNATE CORE SPRAY FABRICATION NA NA NA FABRICATED MODIFICA-CHECK VALVE MODIFI-FC-38-81-2 TION FOR A TEST CON-l CATION MR 0614 NECTION AROUND CHECK VALVE.

RESTAAINTS IN NEW OUTAGE NA NA REPLACED OLD PIPE CONTAINMENT INSTALLATION 81-08 HANGERS WITH NEW SEISMIC W1814 PIPE RESTRAINTS.

REHEATER LEVEL CON-CORRECTIVE OUTAGE ERODED SURFACES EXCESSIVE REPLACED WITH NEW TROL CHAMPER SIGHT MR 3255 81-08 ON THE SEALING STEAM LEAK SIGHT GLASS.

GLASS FACES OF THE FLANGES REHEATER LEVEL CORRECTIVE OUTAGE TEE WAS ERODED STEAM LEAK IN REPLACED TEE, ELBOW AND CONTROL CHAMBER MR 0516 81-08 ON THE INSIDE TEE OF PIPING TWO SHORT PIECES OF PIPE.

AS WAS ELBOW &

SHORT LENGTH OF PIPE REACTOR PLANT B ATTERY NEW OUTAGE NA NA INSTALLED RESTRAINTS TO RACK RESTRAINTS INSTALLATION 81-08 SUPPORT BATTERIES IN MR 0636 CASE OF AN EARTHQUAKE.

N2 BOTTLE RACKS IN NEW OUTAGE NA NA INSTALLED RESTRAINTS TO CONTAINMENT INSTALLATION 81-08 SUPPORT BOTTLES IN CASE MR 0611 OF AN EARTHQUAKE.

m

1 of 3 INSTRUMENT AND ELECTRICAL MAINTENANCE MAY 1981 COUTAGE ITEMS LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMEflT MAINTEflANCE NUMBER CAUSE RESULT CORRECTIVE ACTION SECURITY SYSTEM CORRECTIVE NA UNKNOWN CAMERA OUT OF ADJUSTED CAMERA CAMERA 8 MR 0563 FOCUS FOCUS MR 0586 SECURITY SYSTEM CORRECTIVE NA CHANGE IN AIR DOOR DOES NOT ADJUSTED AUTO CLOSURE CHANGE ROOM DOOR MR 0573 FLOW AUTO CLOSE SECURITY SYSTEM CORRECTIVE NA INCORRECT ALARM CONDI-ADJUSTED SENSITIVITY "E" FIELD MR 0593 ADJUSTMENT

. TION FOUND SECURITY SYSTEM CORRECTIVE NA UNKNOWN ALARM CONDI-ADJUSTED ALARM UNIT ROOF HATCH MR 0600 TION SECURITY SYSTEM CORRECTIVE NA UNKNOWN DID NOT REPLACED AMPLIFIER POLICE FM RADIO MR 0585 RECEIVE CIRCUIT SECURITY SYSTEM CORRECTIVE NA UNKNOWN ALARM CONDI-REPLACED HATCH HATCH DOOR SWITCH MR 0588 TION SWITCH SECURITY SYSTEM CORRECTIVE NA UNKNOWN CAUSING ALARMS ADJUSTED SENSITIVITY MICROWAVE 20-6 MR 0608' SECURITY SYSTEM CORRECTIVE NA UNKNOWN CAUSING ALARMS REBALANCED SYSTEM MICROWAVE 20-2 MR 0612 SECURITY SYSTEM CORRECTIVE NA VACUUM CLEANER BLOWN FUSE REPLACED BLOWN FUSE PLUG STRIP POWER MR 0618 IN VITAL PLUG CCTV OUT OF SUPPLY STRIP SERVICE

  • SECURITY SYSTEM CORRECTIVE OUTAGE CONTAMINATED CTR FUNCTION REPLACED SWITCH CTR FUNCTION OT2-MR 0630 81-08 CONTACTS INOP.
  • SECURITY SYSTEM CORRECTIVE OUTAGE UNKNOWN NO PICTURE REPLACED CCTV CAMERA 4 SECURITY CAMERA 4 81-08

2 of 3 IfiSTRUMEtiT AflD ELECTRICAL MAltiTEtiAtiCE MAY 1981

  • OUTAGE ITEMS lLEROR flATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE fiUMBER CAUSE RESULT CORRECTIVE ACTION
  • SECURITY SYSTEM CORRECTIVE OUTAGE CONTAMINATED CAUSING ALARMS CLEANED SWITCH HATCH ALARM 25-7 MR 0628 81-08 CONTACTS CONTACTS
  • SECURITY SYSTEM CORRECTIVE OUTAGE UNKNOWN CAUSING ALARMS BALANCED SUPERVISORY "E" FIELD 19-7 & 8 MR 0607 81--08' BOARD REACTOR SIGHT GLASS CORRECTIVE NA NORMAL USAGE NO LIGHTS IN REPLACED IAMPS MR 0579 CENTER SECTION OFF-GAS BOOSTER FAN CORRECTIVE NA NORMAL USAGE DEFECTIVE REPLACED MOTOR MR 0584 BEARINGS BEARINGS
  • CHANNEL 7 AGS CORRECTIVE OUTAGE DRIFT LOW CALIBRA-REPLACED MULTIPLIER MULTIPLIER MR 0594~

81-08 TION

  • AREA MONITOR POWER CORRECTIVE OUTAGE NORMAL USAGE LOSS OF POWER REPLACED POWER SUPPLY MR 0595 81-08~

RESISTOR ~

  • RESERVE POWER CORRECTIVE OUTAGE F.C.

FOR FIRE INSTALLED FIRE INSTALLED FIRE CON-TRANSFORMER MR 0620 81-08 SYSTEM SWITCHES TROL SWITCHES

  • SEAL INJECTION CORRECTIVE OUTAGE UNKNOWN OUT OF CALIBRA-RECALIBRATED PRESSURE PRESSURE INDICATOR' MR 0465 81-08 TION INDICATOR-
  • SEAL INJECTION CORRECTIVE OUTAGE NORMAL USAGE RESET PROBLEM REPAIRED LIMIT SWITCH BREAKER 1B MR 0619 81-08 AND LUBE BREAKER
  • CRD SECONDARY POSI-CORRECTIVE OUTAGE NORMAL USAGE DIM LIGHT REPLACED LAMP TION INDICATOR MR 0634 81-08
  • FCP 1A SEAL LEAK-OFF CORRECTIVE OUTAGE EXCESSIVE FLOW CUT SIGHT GLASS REPLACED SIGHT GLASS MR 0639 81-08 i

3 of 3 INSTRUMENT AND ELECTRICAL MAINTENANCE MAY 1981

  • OUTAGE ITEMS LER OR flATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION
  • FUEL GRAPPLE TOOL CORRECTIVE OUTAGE UNKNOWN AIR LEAKAGE REPLACED.O-RING MR 0650 81-08 0 REACTOR PLANT BATTERY PREVENTIVE OUTAGE NORMAL USAGE REPLACED CON-REPLACED CONNECTOR CONNECTIONS MR 0647 81-08 NECTOR LINKS LINKS
  • RADIATION LAB COUNTER CORRECTIVE OUTAGE UNKNOWN NO COUNTS REPLACED CENTER MR 0625 81-08 WIRE AND TRANSISTOR
  • MPT FIRE DETECTION CORRECTIVE OUTAGE FACILITY INSTALLED FIRE INSTALLED FIRE HEADS MR 0615 81-08 CHANGE HEADS 06-81-01
  • NUCLEAR CHANNEL N-1 CORRECTIVE OUTAGE CURVE DRIFT COUNTS TOO COMPLETED DISC.

MR 0638 81-08 HIGH AND HlV CURVE AND SETTINGS

  • NUCLEAR CHANNEL N-5 PREVENTIVE OUTAGE TEST DUE COMPLETED TESTS COMPLETED TESTS FOR THROUGH N-8 81-08 CH N5 THROUGH N8 SAFETY SYSTEM PREVENTIVE NA TESTS DUE COMPLETED TESTS COMPLETED SAFETY CHANNELS 1 AND 2 CH 1 & 2 TESTS
  • TURBINE VACUUM PREVENTIVE OUTAGE TESTS DUE COMPLETED TESTS COMPLETFD VACUUM SWITCHES 81-07.

SYSTEM TESTS

  • NUCLEAR CHANNELS N-1 PREVENTIVE OUTAGE TESTS DUE COMPLETED TESTS COMPLETED TECHNICAL THROUGH N-4 81-07 SPECIFICATION TESTS ON CH N1 THROUGH N4 4ENVIRONMENTAL PREVENTIVE OUTAGE TESTS DUE COMPLETED TESTS COMPLETED AEROVANE AEROVANE 81-07 AND TEMPERATURE TESTS
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