ML19347B577

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Monthly Operating Rept for Sept 1980
ML19347B577
Person / Time
Site: La Crosse File:Dairyland Power Cooperative icon.png
Issue date: 10/03/1980
From: Goodman L
DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML19347B576 List:
References
NUDOCS 8010150373
Download: ML19347B577 (14)
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Text

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l OPERATING DATA REPORT DOCKET NO.

50-409 DATE IU-UJ-UU CO\\tPLETED llY L.S. GOODMAN T ELEPilONE 60R-6A4-2331 1

OPERATING STATUS N"

1. Unit Name: La Crosse Boilina Water Reactor-i
2. Reporting Period: 0000. 09-01-80 to 2400. 09-30-90
3. Licensed Thennal Power tilwt):

165 65.3

4. Nameplate Rating IGrow AlWel:
5. Design Electrical Rating iNet alwel:
6..\\tatimum Dependable Capacity (Grow.\\lhel:

50

7..\\tasimum dependable Capacity (Net SlWel:

40 S. If Changes Occur in Capacity Ratings titems Number 3 Through 7) Since Last Report. Gise Reamns:

9. Power Level To Which Restricted. lf Any (Net Sther
10. Reasons For Restrictions. If An):

j This Stonth Yr to-Date Cumulati e

11. Ilours in Reporting Period 720 6E75 og gon
12. Number Of flours Reactor has Critical 644.7 5347.6 6 0 si 7*
13. Reactor Resene Shutdown flour, 0

0 478 T93.6 5095.4 58.100.2

14. Ilours Generator On Line
15. Unit Resene Shutdown floun 0

0 79 7

16. Grow Thermal Energy Generated 1.\\lWil; 80.701.0 677.967.4 7.o67_747_o 17 Grow Electrical Energy Generated I\\ twill 23,314___._ _,

196.185

.2,395 M

~

18. Net Electrical Energy Generated IMWHI 21,638 182.435 2.215.170 82.4 77.5 60.7 1
19. Unit Senice Factor
20. Unit Asailability Facto, 82.4 77.5 60.8
21. Unit Capacity r' actor tusing \\lDC Nei, 62.6 57.8 48.2 60.1 55.5 46.3 22 Unit Capacity Factor (Using Dtd NetI
23. Unit Forced Outage Rate 17.6 14.6 7,2
24. Shutdowns Scheduled Oser Nest 6 \\lonthsiType,llate, and Duration of Eacht ESTIMATED REFUELING OUTAGE. NOVEMBER 10. 1980. 6 WEEKS
23. II Shut Down At I nd Of Report Period. Estimated Date of St.rtup
26. Um s in Test Status (Prior to Commercial Operations forecast Achiesed INill\\l.t Hillt'il_Il Y INill\\lIlitIRitIIY

( O\\l\\ll Rt I \\l Ol'l R \\ IION

  • Corrected for.6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> roundoff errors incurred 1977-1978.

t soloiso 373

d AVERAGE DAILY UNIT POWER LEVEL f

DOCKET NO.

50-409 31T. LACBWR 10-03-80 DATE L.S. GOOD N COMPLE'ITD BY TELEPilONE

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I MONTil

. SEPTEMBER 1980 1

DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL IMWe-Net)

(MWe. Net) 1 0

38 g7 0

is 38 3

0 19 38 0

1 4

o 3g 5

1 38 6

3 22 38 7

24 23 38

(

s 35 24 38 9

38

s 38 38 to 26 38 38 27 38 1

38

s 38 13 38 38 29 14 38 3o 38 is 38 3

16 38 i

INSTRL'CTIONS On this lorrnat. fist the average daily unit power levelin MWe Net for each day in the reporting snonth.Cionpute to the nearest whole twrawart.

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j NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 4

SEPTEMBER 1980 1

1 At the onset of the September reporting period, the plant remained in a shutdown condition while maintenance commenced during the August 22, 1980 outage was l

completed and prestartup tests were performed.

1 i

On September 3, at 1655, the reactor was returned to critical. At 2220 on j

September 4, the LACBWR turbine-generator was connected to the DPC grid and slow escalation commenced.

i On September 5, at 0700, a partial scram occurred from 31% Reactor Rated Thermal Power, due to water leakage, from the seal inject supply line connection to Control Rod Drive Mechanism (CRDM) No.1, spraying onto the scram olenoid area i

of CROM No. 3 and causing an electrical short. The seal inject supply connection J

was tightened and the inboard scram solenoid on CRDM No. 3 was replaced.

At 1725, on September 5, the reactor was returned to critical and at 1504 on September 6, the turbine-generator was synchronized to the DPC grid.

i l

Power escalation continued until September 8, when 85% Reactor Rated Thermal Power (38 MWe-Net) was achieved. Power generation continued at this level

]

throughout the remainder of the reporting period.

This operating power level j

has been scheduled to stretch optimum production until refueling becomes necessary.

l Significant maintenance items performed during the September 1980 reporting period are indicated on the attached Instrument and Electrical Maintenance acd Mechanical Maintenance listings.

4 0

1 of 2 DOCKEi NO.

50-409 UNIT SilUIDOWNS AND POWER REDUCTIONS UNIT N AME LACBWR 10'U3-UU DATE REPOR T MON 711 SEPTEMBER 1980 COMPLETED BY L.S. GOODMAN TELEPHONE 608-689-2331

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Licensu 3 +,

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Date i

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Esent

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Atieon to j5-ReporI e nV j'

Preveni Recurrente 5

80-08 08-22-80 F

94.3 A

3 NA CH INSTRU THE AUGUST OUTAGE DUE TO THE TRIPPING OF 1A REACTOR FEED PUMP WAS COMPLETED.

WHILE THE PLANT WAS SHUTDOWN, MATNTEN-ANCE WAS ALSO PERFORMED ON THE SEAL INJECT SYSTEM AND THE MECHANICAL SEALS IN CONTROL R00 DRIVE MECHA" ISMS N05. 5 AND 21.

80-09 09-05-80 F

32.1 A

3 NA RB CRDRVE WATER LEAKAGE l10M THE SEAL INJECT SUPPLY LINE C0ll';ECTION TO CONTROL R00 DRIVE MECHANISM NO. 1 SPRAYED ONTO THE SCRAM SOLEN 0ID AREA 0F CRDM NO. 3, CAUSING AN ELECTRICAL SHORT, RESULT-ING IN A PARTIAL SCRAM. THE SEAL IN-JECT SUPPLY LINE WAS PROBABLY BUMPED, CAUSING THE CONNECTION TO LOOSEN DUR-ING MAINTENANCE PERFORMED IN OUTAGE 80-08. THE SEAL INJECT LINE CONNECT-ION AT CRDM N0. 1 WAS TIGHTENED AND

.... (Con t' d )

i 3

F l'orted Reason :

Method:

Eidubit G - Inst ructions S: Schedufed A-l'quipment l'ailure (l.splain)

! -Man ual for Preparation of Data B Maintenance or Test

.' M.inisal So.un.

Entr> Sheets for luensee C Refuel.ng 3 Antoinstic Sci sin.

1%ent Repost (1.1. R n l'ife ( Nt'RI G.

D NegulJtor) RestrictnpH 4-Other (I spIJip) 01bll 1 -Operator Tranung & L,ense i ummation I Adnunistratise i

G-Operational I iror il splain)

ITtubit 1 Same Source P8l77)

Il-Ot her (INplain i

2 of 2 50-409 UNil SilU1 DOWNS AND POWI.R REDUCTIONS DOCKET NO.

UNIT N AME LACBWR COMRETE 8 W

REPORT MONfli SFPTFMPFR 1980 TELEPHONE WRQ 9111 e

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h l.itenset E-Causc A forrestive 55' 5?

Action to

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$2 d

35:

Repost c

$0

[L Pscient Ret urrente u

6 THE INBOARD SCRAM SOLEN 0ID COIL ON CRDM NO. 3 W^S REPLACED.

l 2

1 4

I l'or ed Reason:

Method Estubit G-Instructions s

S h hedufed A l~quipment failure (1 splam)

! Mmual for Pseparation of Data H. Maintenance or Test

'. Autornat h M r.im.

1 ntry Sheets t'on I.scensee

. Manual Scram.

C. Refueling t

I.sent Report 11.1 R)I'ile (NI:RI G-D.R. Fulatory Restration 4 Othes t I splaud 0161 I -Operatos Traming A l.ssenw I saiinnaison F-Adnumst ratise G4)perational l a vor (l'spland I sinha i. s3,n.. s,u:6e i:7 7 )

ll Other (Esplaml i

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SEPTEMBER 1980 INSTRUMENT AND ELECTRICAL MAINTENANCE 1 of 2 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION NUCLEAR INSTRUMENTATION CORRECTIVE NA DEFECTIVE TUBES INCORRECT INDI-REPLACED DIODE AND TUBES 4

CHANNEL N-1 MR 0018 CATION NUCLEAR INSTRUMENTATION PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED TECHNICAL SPEC-IFICATION TEST N-5 THROUGH N-9 SAFETY SYSTEM PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED SAFETY SYSTEM TECHNICAL SPECIFICATION TESTS FOR CH. 1, 2, AND H O #3 2

FIRE DETECTION PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED FIRE DETECTOR TESTING FORCED CIRCULATION IB CORRECTIVE OUTAGE NORMAL USAGE IMPROPER OPERATION REPLACED PILOT VALVE DISCHARGE VALVE POSITIONER MR 3366 80-08 ASSEMBL)

REACTOR VENT FAN CORRECTIVE OUTAGE OVERHEATING BEARING BURN 0UT REPLACED MOTOR BEARINGS MR 3367 80-08 BEARINGS RADIATION MONITORING PREVENTIVE OUTAGE MAINTENANCE DUE COMPLETED CLEANED AND TESTED MR 3325 80-08 MAINTENANCE PORTAL MONITOR SEAL INJECTION SYSTEM PREVENTIVE OUTAGE MAINTENANCE RE-CHECKED ALL EOUIo-CHECKED SEAL INJECTION MR 3250 80-08 QUEST MENT TRANSMITTER, CONTROLLER MR 3364 I/P CONVERTER, BOOSTER CONTROL R0D DRIVE #3 CORRECTIVE OUTAGE WATER LEAKAGE BURNED OUT REPAIR LEAK, REPLACE COIL MR 3370 80-09 S0LEN0ID REACTOR FEED PUMP CORRECTIVE OUTAGE AUXILIARY CONTACT BREAKER INOPERATIVE REALIGNED CONTACT R0D 4

BREAKER MR 3373 8 0- 09 R0D BENT REHEATER RECORDER CORRECTIVE NA MECHANICAL BINDING RECORDER IN0PERA-REPAIRED PEN MECHANISM MR 3384 TIVE I

CONTROL R0D SECONDARY CORRECTIVE NA NORMAL USAGE FULL OUT LAMP REPLACED LAMP FOR UNIT POSITION INDICATION MR 3393 IN0 PERATIVE

  1. 18 a

SEPTEMBER 1980 INSTRUMENT AND ELECTRICAL MAINTENANCE 2 of 2 LER OR

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NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION l

RADIATION MONITORING PREVENTIVE NA TEST DUE COMPLETED TESTS COMPLETED BI-WEEKLY RADIATION CHECKS 4

SECURITY SYSTEM "E" FIELD CORRECTIVE NA UNKNOWN INOPERATIVE REALIGNED BALANCE AND MR 3359 TESTED UNITS SECURITY SYSTEM CARD CORRECTIVE NA UNKNOWN INOPERATIVE ADJUSTED SENSITIVITY READER MR 3358 SECURITY SYSTEM CCTV CORRECTIVE NA UNKNOWN IMPROPER PICTURE REALIGNED AUTO LENSE CAMERA #7 MR 3372 ADJUSTMENT i

SECURITY SYSTEM CRIB CORRECTIVE NA DEFECTIVE IMPROPER ALARt'S REPLACED VOLTAGE HOUSE ALARM UNIT MR 3392 REGULATOR REGULATOR SECURITY SYSTEM CRT CORRECTIVE NA SH,P.T IN HIGH INOPERATIVE CRT REPAIRED SHORTED

)

IN SAS VOLTAGE WIRING SECURITY SYSTEM MICR0 CORRECTIVE NA UNKNOWN IMPROPER ALARMS ADJUSTED AND BALANCED WAVE SYSTEM MR 0003 THE SYSTEM MR 0007 MR 0015 SECURITY SYSTEM CCTV CORRECTIVE NA NORMAL USAGE P00R PICTURE REPLACED VIDICON TUBE CAMERA #3 MR 0019 i

j SECURITY SYSTEM CCTV CORRECTIVE NA NORMAL USAGE P00R PICTURE REPLACED VIDICON TUBE CAMERA #1 MR 0018 SECURITY SYSTEM "E" CORRECTIVE NA UNKNOWN IMPROPER ALARMS ADJUSTED AND BALAhCED FlELD MR 0020 UNIT i

SEPTEMBER 1980

~

_ {CI!ANICAT, MAINTFNANCI' M

LER nR NATURE OF OUTAGE MALFUNCTIO'i EQUIPMENT MAINTENANCE NUPEER CAUSE RESULT CORRECTIVE ACTIC'4 WASTE WATER SUCTION VALVE CORRECTIVE OUTAGE BROKEN DIAPHRAGM LEAKED THROUGH REPLACED BONNET AND (3000 GALLON WASTE TANKS)

MR 3356 80-0 DIAPHRAGM CONTROL ROD DRIVE IN CORRECTIVE OUTAGE DEFORMED 0-RING OIL LEAK REPLACED NEW 0-RING POSITION NO. 5 MR 3370 80-09 PACKING AT OIL PACKING CHARGING CONNEC-TION AT HEADER 1B SEAL INJECTION PUMP CORREC71VE OUTAGE RUBBER SEAT WAS LEAKED THROUGH REPLACED RUBBER SEAT AND DISCHARGE CHECK VALVE MR 3365 80-08 WORN LAPPED DISC.

  1. 52-26-002 REACTOR VENT FAN MOTOR CORRECTIVE OUTAGE WORN BEARING EXCESSIVE REPLACED MOTOR MR 3362 80-08 VIBRATION UPPER CRD #1 CORRECTIVE OUTAGE JAM NUT LOOSE WATER LEAKAGE TIGHTENED JAM NUT MR 3369 80-09 CONTROL ROD DRIVE IN CORRECTIVE NA DEFORMED 0-RING OIL LEAK REPLACED 0-RING PACKING POSITION NO.10 MR 3387 PACKING AT OIL CHARGING HOSE CONNECTION 1A AND IB STATION AIR PREVENTIVE NA NONE NONE C0!G.ETED 3-YEAR P.M.

COMPRESSOR MAINTENANCE 3-YEAR P.M.

MR 0027 MR 3395 IB 0FF-GAS DRYER CORRECTIVE NA SOLDER JOINT LOST FREON RESOLDERED AND RECHARGED MR 3383 BROKE WITH FREON

Pg. 1 of 2 REFUELING INFORMATION RE0 VEST 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 (E0C-VI) is November 10, 1980.

3.

Scheduled Date for Restart Following Refueling:

The tentatively scheduled date for subsequent reactor startup is December 22, 1980.

l 4.

Will Refuelina or Resumption of Operation Thereaf ter Recuire a Technical Specification Change or Other License Amendment?

If answer. is yes, what in ceneral, will these be?

I If answer is no, has the reload fuel desien and core conficuratica been reviewed by your Plant Safety Review Conni'. tee to determine whether any unreviewed safety ouestions are associated with the core reload (Ref.

10 CFR 5ection 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 subsecuent resumption of operation.

The Safety Review Committee's 50.59 review of the reload fuel design and core configuration will be conducted during their October 1980 meeting.

5.

Scheduled Date(s) for Submitting F-ooosed Licensina Action and Sucoortino Information.

NA 6.

Important Licensing Considerations Associated with Refuelino, e.a.,

New or Different Fuel Design or Supplies, Unreviewed Desinn or Performance Analysis Methods, Significant Chances in Fuel Desion, New Operating ~ Procedures.

i 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 r---

Pg. 2 of 2 4

i REFUELING INFORMATION REQUEST - (Cont'd) 8.

The Present Licensed Spent Fuel Pool Storage Capacity and the Size of any Increase in Licensed Storage Capacity that has been Reouested or so Planned, in Number of Fuel Assemblies.

LACBWR is presently in the process of increasing the spent fuel pool storage capacity from 134 to 440 fuel assemblies.

Estimated completion date is November 3, 1980.

l 9.

The Frojected Date of the Last Refuelina that can be Discharaed to the Spent Fuel Pool Assuming the Present Licensed Capacity.

4 1990 E

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