ML20050B105

Monthly Operating Rept for Jan 1982

ML20050B105
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	02/03/1982
From:	Goodman L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML20050B102	List: ML20050B101 ML20050B105
References
NUDOCS 8204050007
Download: ML20050B105 (15)

Text

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OPERATING DATA REPORT DOCKET NO..50-409 DATE 02-03-82 COMPLETED BY L.S. GOODMAN TELEPilONE. 608-689-2331 OPERATING STATUS Notes

1. Unit Name: LA CROSSF ROTI INI, WATFR RFACTOR

2. Reporting Period: 0001. 01-01-82 TO 2400. 01-31-82

3. Licensed Thermal Power (MWt):

165

4. Nameplate Rating (Gross MWe):

65.3 50

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

50

7. Maximum Dependable Capacity (Net MWe):

48

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions,if Any:

This Month Yr..to.Date Cumulative

!I. Ilours In Reporting Period 744 744 107.403

12. Number Of flours Reactor Was Critical 207.3 207.3 71,338.6

13. Reactor Reserse Shutdown llours 0-0-

478 i

14. Ilours Generator On-Line 139.0 139.0 65.831.2

15. Unit Reserve Shutdown Hours 0

0 79

16. Grow Thermal Energy Generated (MWH) 13,979.3 13,979.3 9,009,768.1

17. Grow Electrical Energy Generated (MWH) 3.475 ___

__. 3.475 2.693.333

18. Net Electrical Energy Generated (MWH) 2.714 2.714 2.490.706

19. Unit Service Factor 18.7 18.7 61.3

20. Unit Availability Factor 18.7 18.7 61.4

21. Unit Capacity Factor (Using MDC Net) 7.6 7.6 48.3 l

22. Unit Capacity Factor (Using DER Net) 7.3 7.3 46.4 l

23. Unit Forced Outage Rate 81.3 81.3 8.2

24. Shutdowns Scheduled Oser Next 6 Months (Type. Date,and Duration of Each):

REFUELING OUTAGE. MARCH 19.1982. 6 WEEKS

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

NA

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

Forecast Achiesed l

INITIA L CRITICALITY INITIAL ELECTRICITY COMMERCI AL OPER ATION l

l B204050007 820208 l

PDR ADOCK 050C0409 (9/77 )

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INSTRUCTIONS FOR COMPLETING OPERATING DATA REPORT

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i Tlus report should be furnished each month by licensees. The name and telephone number of the preparer should be provided in the designated spaces. The instructions below are provided to assist licensees in reporting the data consistently. The number of the instruction corresponds to the item number of the report format.

1. UNIT 'iAME. Self explanatory.

or of commercial operation, whichever comes last, to the end of the period or decommiss'aning, whichever comes

2. REPORTING PERIOD. Designate the month for which first. Adjustments in clock hours should be made in the data are presented, which a change from standard to daylight-savings time (or vice versa) occurs.

s

3. LICENSED TilERMAL POWER (MW )is the maximum thermal power, expressed in megawatts, currently auth-

12. NUMBER OF HOURS REACTOR WAS CRITICAL.

orized by the Nuclear Regulatory Commission.

Show the total number of hours the reactor was critical during the gross hours of the reporting period.

4. NAMEPLATE RATING (GROSS MW,). The nameplate power designation of the turbine generator in megavoit

13. REACTOR RESERVE SilUTDOWN 110URS. The total amperes (MVA) times the nameplate power factor of the number of hours during the gross hours of reporting turbine generator.

period that the reactor was removed from service for administrative or other reasons but was available for

3. DESIGN ELECTRICAL RATING (NET MW,) is the operation.

nominal net electrical output of the unit specined by the utility and used for the purpose of plant design.

14. HOURS GENERATOR ON.LINE.

Also called Service llours. The total number of hours expressed to the near-

6. MAXIMUM DEPENDABLE CAPACITY (GROSS MW,)

est tenth of an hour during the gross hours of the re-is the gro; electrical output as measured at the output porting period that the unit operated with b:eakers terminals of the turb;ne-generator during the most re*

closed to the station bus. These hours, plus those listed strictive seasonal conditions.

in Unit. Shutdowns for the generator outage hours,should

7. MAXIMUM DEPENDABLE CAPACITY (NET MW, h Maxiroum dependaole capacity (gross) !ess the normal

15. UNIT RESERVE SilUTDOWN 110URS. The totat num-station service loads.

ber of hours expressed to the nearest tenth of an hour during the gross hours of the reporting period that the

8. Self-explanatory.

unit was removed from service for economic or similar I

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9. POWER LEVEL TO WillCil RESTRICTED, IF ANY (NET MW ).

Note that this item is appheable only if

16. GROSS TilERMAL ENERGY GENERATED (MWii).

e restrictions on the pcwer level are in effect. Short-tenn (less than one month) limitations on power level need The thermal output of the nuclear steam supply system during the gross hours of the reporting period, expressed not be presented in this item.

n megawatt hours (no decimals).

Since this information is used to develop figures on capa-city lost due to restrictions and because most users of the

17. GROSS ELECTRICAL ENERGY GENERATED (MWil).

" Operating Plant Status Report" are primarily interested The electrical output of the unit measured at the output in energy actually fed to the distribution system. it is terminals of the turbine-generator during the gross hours requested that this Ogure be expressed in MWe. Net in of the reporting period, expressed in megawatt hours (no spite of the fact that the figurc must be derived from decimals).

MWt or percent power.

18. NET ELECTRICAL ENERGY GENERATED (MWll).

10. REASONS FOR RESTRICTIONS, IF ANY. If item 9 The gross electrical output of the unit measured at the is used, item 10 should explain why. Brief narrative is output terminals of the turbine-generator minus the nor-acceptable. Cite references as appropriate. Indicate mal station service load, during the gross hours of the whether restrictions are self-imposed or are regulatory reperting period, expressed in megawatt hours. Negative requirement s. Be as specific as possibic within space limi-quantities should not be used. If there is no net positive tations. Plants in startup and power ascension test phase value for the period, enter zero (no decimals).

should be identined here.

11. Il0URS IN REPORTING PERIOD. For units in power

19. For units still in the startup and power ascension test ascension at the end of the period, the gross hours from

23. phase. items 19-23 should not be computed. Instead enter the beginning of the period or the first electrical produe-N/A in the current month column. These Ove factors tion, whichever comes last, to the end of the period.

should be computed starting at the time the unit is de-clared to be in commercial operation. The cumulative For umts in commercul operation at the end of the Ogures m the second and thud columns should be based i

period, the gross hours from the beginning of the period on commercial operation as a starting date (9/77 )

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19. UNIT SERVICE FAC10R. Compute by dividmg hours e

the generator was on line (item 14) by the gross hours in the reporting period (item 11). Express as percent to the nearest tenth of a percent. Do not include reserve shut-down hours in the calculation.

20. UNIT AVAILAlllLITY' FACTOR. Compute by dividing the unit available hours (item 14 plus item 15) by the J

gross hours in the reporting period (item 1!). Express as percent to the nearest tenth of a percent.

21. UNIT CAPACITY FACTOR (USING SIDC NET). Com-pute by dividing net electrical energy generated (item 18) by the product of maximum dependable capacity (item

7) times the gross hours in the reporting period (item 11).

Express as percent to the nearest tenth of a percent.

22. UNIT CAPACITY FACTOR (USING DER NET). Com-pute as in item 21. substituting design electrical rating (item 5) for maximum dependable capacity.

23. UNIT FORCED OUTAGE RATE. Compute by dividing the total forced outage hours (from the table in Unit Shutdowns and Power Reductions) by the sum of hours generator on line (item 14) plus total forced outage hours (from the table in Unit Shutdowns and Power Reductions).

Express as percent to the nearest tenth of a percent.

24. SilUTDOWNS SCHEDULED OVER NEXT 6 510NTliS (TYPE, DATE, AND DURATION OF EACil). Include type (refueling, maintenance, other), proposed date of start of shutdown, and proposed length of shutdow i.

It is recognized that shutdowns may be scheduled betwren j

reports and that this item may not be allinclusive. lie as accurate as possible as of the date the report is prepared.

This item is to be prepared each month and updated if appropriate undl the actual shutdown occurs.

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25. Self explanatory.

26. Self explanatory. Note, however, that this information is requested for all units in startup and power ascension test status and is not required for units already in com.

mercial operation.

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TEST STATUS ts defined as that period fallowing ini-l tial criticality during which the unit is tested at succes-sively higher outputs, culminating with operation at full power for a sustained period and completion of war-ranty runs. Following this phase, the unit is generally considered by the utility to be available for commercial operation.

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D.ite of CO%!\\lERCIAL OPERATION is defined as the date that the unit was declared by the utility owner to be available for the regular production of electricity.

l usually related to the satisfactory completion of quali-l fication tests as specified in the purchase contract and to the accounting policies and practices of the utility.

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-409 LACBWR UNIT 82 DATE COMPLETED BY L.S. GOODMAN 608-689-2331 TELEPHONE MONTil JANUARY, 1982 DAY AVER AGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 0

17 0

O 0

18

~

0 0

'i 19 0

0 4

20 0

0 5

21 0

0 6

22 0

0 7

23 0

0 8

24 0

0 9

25 10 0

8 26 18 27 0

22 12 28 0

25 13 29 0

28 I

l1 30 0

is 31 30 16 0

i INSTRUCTIONS i

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

1 (9/77) l

Page 1 of 2 50-409 DOCKET NO.

UNIT SHU1 DOWNS AND POWER REDUCTIONS UNIT N AME LACBWR DATE 02-03-82 JANUARY 1982 COMPLETED BY

_L,S. GOODMAN REPORT MONTil TELEPHONE 6f1A-6RQ 7111 j?

3 hY Licensec

,Eg Cause & Corrective f'3 No.

Dale i

3g i;

2s5 Event

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n-Action to

$2 E

j5=

Report e EU Present Recurrence H

6 81-19 12-23-81 F

597.2 A

3 LER-81-14 XX XXXXX CONTINUATION OF DECEMBER 1981, OUTAGE 82-01 1-25-82 F

2.2 A

4 NA IIA MECFUN GENERATION WAS TEMPORARILY RE-MOVED FROM THE DPC GRID DURING OUTAGES 82-01, 82-02 AND 82-03.

DUE TO MALFUNCTION OF 81-19 1-26-92 F

0.3 A

4 NA IIA MECFUN THE TURBINE GOVERNOR SYSTEM INITIAL PRESSURE REGULATOR (IPR).

AN AIR LEAK WAS FOUND ON THE NEW IPR POSITIONER, 82-03 1-26-82 F

5.3 A

4 NA HA MECFUN WHICH HAD BEEN INSTALLED DURING OUTAGE NO. 81-19, AS PART OF Tile PM PROGRAM.

AN i

(Cont'd on 2 of 2)

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A. Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D-Regulato y Restriction 4-Ot her ( Esplain) 0161) 1:-Operator Training & license INamination F-Administratise 5

G-Operational Error (Explain)

Exhibit I - Same Source p8/77)

Il Other (lhplain)

W Page 2 of 2 DOCKET NO. 50-409 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT N AME LACBWR DATE 02-01-92 COMPLETED BY L S 00nw AN REPORT MONTH JANUARY 1982 TELEPHONE 60R-694-?til 3

.5 -

"h Yk Licensee

,En, Cause A Corrective No.

Date i

52 i

.5 i $

Event 3?

El Action to

$5 jig Report e NO j'

Present Recurrence H

d 0-RING WAS REPLACED.

NEW POSITIONERS WILL BE CHECKED PRIOR TO INSTALLATION IN TILE FUTURE.

THE REACTOR WAS NOT SHUT DOWN DURING THESE OUTAGES.

I 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A. Equipment Failure (Explain) 1-Manual for Preparation of Data B Maintenance of Test 2-Manual Scram.

Entry Sheets for Liernsee C Refueling 3 Automatic Scram.

Event Report (LER) File iNUREG.

D-Regulatory Restriction 4-Other ( Explain) 0161)

E Operator Training & Ueense Examination F-Administratise 5

G-Operational Error (Explain)

Exhibit 1 - Same Source 19/77)

Il-Other ( E xplain)

JANUARY 1982 SHEET 1 of 4 INSTRUMENT AND ELECTRfCAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION NUCLEAR INSTRUMENTA-PREVENTIVE OUTAGE TESTS DUE COMPLETED TESTS COMPLETED TESTS N-5 TION CHANNELS 5 81-19 THROUGH N-9 THROUGH 9 AUTOMATIC GAIN SYSTEM PREVENTIVE OUTAGE REQUEST COMPLETED TESTS REPLACED MULTIPLIER CH 6 (AGS) CHANNELS 6 & 8 81-19 SAFETY SYSTEM CH 1, PREVENTIVE OUTAGE TESTS DUE COMPLETED TESTS COMPLETED SAFETY H 0, NO. 3 81-19 SYSTEM TESTS 2,

2 NUCLEAR CH N8 PREVENTIVE OUTAGE REQUEST COMPLETED TESTS COMPLETED N8 TECH MR-0080 81-19 SPEC TEST NUCLEAR CH N-5 CORRECTIVE OUTAGE RECORDER AMP RECORDER INOP-REPLACED AMPLIFIER RECORDER MR-1031 81-19 DEFECTIVE ERATIVE IN RECORDER NUCLEAR CH N-6 CORRECTIVE OUTAGE MULTIPLIER INCORRECT READ-REPLACED WITH SPARE MR-0023 81-19 DRIFT ING

. UNIT POWER FLOW LOCKOUT NEW INSTALLATION OUTAGE FC-41-81-1 COMPLETED COMPLETED INSTALLATION RELAYS FC-41-81-1 81-19 INSTALLATION MR-0013 FORCED CIRCULATION FACILITY CHANGE OUTAGE FC-50-81-3 REMOVED ALARM REMOVED ALARM UNITS PUMP (FCP) FACE SEAL FC-50-81-3 81-19 UNITS TEMPERATURE ALARMS MR-0954 MR-0973 MR-0029 RADIATION AREA MONITOR CORRECTIVE OUTAGE RELAY BURNOUT POWER SUPPLY REPLACED RELAY AND POWER SUPPLY 1-10 MR-0014 81-13 INOPERATIVE RESISTOR, TUBE RADIATION ENVIRONMENT-CORRECTIVE OUTAGE USAGE PUMP INOPERATIVE REPLACED PUMP AND MOTOR AL SAMPLE PUMP MR-0034 81-19 i

RADIATION MOBILE CORRECTIVE OUTAGE LOOSE WIRE ON ALARM INOPER-REPLACED WIRE AND MONITOR MR-0028 81-19 ALARM ATIVE TESTED RADIATION kEACTOR CORRECTIVE OUTAGE USAGE CHART DRIVE REPLACED DRIVE CAVITY MONITOR MR-0047 INOPERATIVE MECHANISM RECORDER

TANUARY 1982 SIIEET 2 of 4 INSTRUMENT AND ELECTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION GENERATOR EXCITATION PREVENTIVE OUTATE REQUESTED TEST COMPLETED TEST COMPLETED TEST SYSTEM TEST MR-1090 81-19 LER-81-14 CONTROL ROD DRIVE (CRD)

PREVENTIVE OUTAGE OVERilAUL COMPLETED TESTS COMPLETED TESTS NO. 3 MR-0989 81-19 SECURITY ENTRY CAMERA CORRECTIVE OUTAGE AMPLIFIER INOP-PICTURE INOP-REPLACED AMPLIFIER MR-0032 81-19 ERATIVE ERATIVE SECURITY CAMERA 20-4 INSTALLATION OUTAGE AUTO SWITCIIER REINSTALLATION REINSTALLATION MR-0036 81-19 SECURITY CONTROL ROOM CORRECTIVE OUTAGE UNKNOWN READER DEFEC-REPLACED WITH SPARE ENTRY READER MR-0031 81-19 TIVE SECURITY TERMINAL CORRECTIVE OUTAGE UNKNOWN RETURNED FROM REINSTALLED AFTER CRT CARD MR-1091 81-19 REPAIR REPAIR SECURITY ALARM CARD CORRECTIVE OUTAGE UNKNOWN FALSE ALARMS REPLACED WITil SPARE 1

20-6 MR-0082 81-19 ALARM CARD REACTOR VESSEL TEMPER-CORRECTIVE OUTAGE USAGE DRIVE STRING REPLACED DRIVE STRING ATURE RECORDER MR-1107 81-19 BROKEN WASTE WATER TOTALIZER CORRECTIVE OUTAGE USAGE TOTALIZER IN-INSTALLED NEW MR-1097 81-19 OPERATIVE TOTALIZER SEAL INJECTION 1A CORRECTIVE OUTAGE OVERilAUL CllECKED STROKE COMPLETED STROKE TEST BYPASS VALVE MR-0697 81-19 AIR COMPRESSOR 1A OIL CORRECTIVE OUTAGE USAGE ALARM INOPER-CLEANED SWITCil MECll-LEVEL SWITCll MR-0952 81-19 ERATIVE ANISM l

JANUARY 1982 INSTRUMENT AND ELECTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION CRD IN-OUT CONTROL PREVENTIVE OUTAGE PREVENTIVE REPLACED REPLACED WITil SPARE SWITCil MR-1111 81-19 MAINTENANCE SWITCII UNIT (PM) DUE 3-WAY INJECTION CORRECTIVE OUTAGE OVERilAUL RESTROKED VALVE RESTROKED VALVE VALVE 1B FCP MR-0009 81-19 IPR POSITIONER PREVENTIVE &

OUTAGE PM DUE; CYLIN-IMPROPER REBUILT SPARE CORRECTIVE 82-01, DER NOT PRE-

RESPONSE

INSTALLED, REPLACED MR-0012 82-02, LOADED AND O-RING 82-03, ROLLED O-RING 81-19 2400 VOLT SWITCH-CORRECTIVE OUTAGE REQUEST TESTED ALL TESTED AND ADJUSTED GEAR MR-0017 81-19 BREAKERS ALL BREAKERS LER-81-14 TURBINE VIBRATION MG CORRECTIVE OUTAGE USAGE BAD BEARINGS INSTALLED NEW BEARINGS SET MR-0896 81-19 STATIC INVERTER 1B CORRECTIVE OUTAGE USAGE SLOW FANS CLEAN AND LUBRICATED MR-0893 81-19 FAN MOTORS ECCS 1B CONT.

CORRECTIVE OUTAGE UNKNOWN BREAKER INOP-REALIGNED BENT BREAKER MR-0895 81-19 ATIVE LINKAGE CONTROL ROD DRIVE CORRECTIVE NA NORMAL USAGE LAMP INOPER-REPLACED LAMPS FOR SECONDARY POSITION MR-0048 ATIVE NOS. 11 AND 17 DIESEL GENERATOR 1B CORRECTIVE NA SNOW AND ICE SilORT IN LOAD TIIAWED ICE OUT AND TEST LOAD MR-0050 BANK TESTED OK

I JANUARY 1982 1

INSTRUMENT AND ELECTRICAL MAINTENANCE i

LER OR

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NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION ANNUNCIATOR PANEL "E"

CORRECTIVE OUTAGE USAGE COIL BURNOUT REPLACED COIL MR-0070 81-19 FIRE DETECTOR ZONE 18 CORRECTIVE NA CONTAMINATION FALSE ALARM CLEANED FIRE DETECTOR MR-0079.

FCP IB SEAL LEAK-OFF PREV.dNTIVE', '

NA,.-

ALARM ON~

REQUEST TO INCREASED ALARM POINT

^

l ALARM MR-0091 CONTINUOUSLY INCREASE ALARM

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INSTALL AREA EVACUA-NEW INSTALLATION NA NEW INSTALL-COMPLETED COMPLETED TESTING

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TION SIREN ATION INSTALLATION l

T PROTECTIVE RELAYS PREVENTIVE OUTAGE' REQUEST COMPLETED TESTS COMPLETED TESTING AND MR-1090 81-19 SETTINGS ON GENERATOR l

LER-j 81-14

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BUS PROTECTIVE RELAYS f

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SCRAM CIRCUITRY PREVENTIVE OUTAGE UNEXPLAINED REQUEST TO

^ CHECKED,' CLEANED ASU I

~

81-19 SCRAM CHECK' SCRAM

'OPER'ATEMCONTACTS IN t

CIRCUITRY FULL SCRAM CI,RCUITRY

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Page 1 of 3 l

MECIIANICAL MAINTE!!ANCE JANUARY 1982 i

LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION REHEATER LEVEL CORRECTIVE OUTAGE FLEX GASKET STEAM LEAKAGE LAPPED FLANGES AND CONTROL CHAMBER MR-0956 81-19 STEAM CUT REPLACED FLEX GASKETS L

1A FORCED CIRCULATION CORRECTIVE OUTAGE PACKING OLD STEAM LEAK REPACKED WITH NEW l

j PUMP (FCP) DISCHARGE MR-1088 81-19 AND STEAM CUT PACKING AND HAD i

ROTOPORT LEAK REPAIR INC.

PUMP A LIQUID-TYPE PACKING INTO THE j

GLAND, WITH ONLY TWO GLAND BOLTS IN PLACE l

SEAL INJECTION CORRECTIVE OUTAGE PACKING FROM WAS NOT ALLOW-REPLACED ALL INTERNALS l

BYPASS VALVES MR-069 7 81-19 PUMP GOT INTO ING ALLOWING IN 1A VALVE, INSTALLED

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THE VALVE PROPER FLOW CLEANED STACK AND NEW PORTS STEM IN 1B 1

)

HIGH PRESSURE SERVICE CORRECTIVE OUTAGE SEAT AND DISC VALVE LEAKED' REPLACED VALVE WATER (HPSW) TO CON-MR-1049 81-19 WERE WASHED THROUGH TAINMENT BUILDING OUT f

i 701' LEVEL, VALVE NO. 62-25-005 l

1A SHIELD COOLING CORRECTIVE OUTAGE MECHANICAL SEAL LEAKED INSTALLED NEW SEALS PUMP MR-1101 81-19 SEAL WORN OUT THROUGH i

!HVA PILOT VALVE FOR CORRECTIVE OUTAGE BODY WASHED LEAKED THROUGH, INSTALLED NEW BODY, i

j 1B FCP DISCHARGE MR-1016 81-19 OUT NOT LETTING OLD INTERNALS ROTOPORT VALVE OPERATE i

l SHUTDOWN CONDENSER CORRECTIVE OUTAGE SEAT AND DISC VALVE LEAKED INSTALLED NEW VALVE-i TRAP BYPASS NO.

MR-0937 81-19 WERE CUT THROUGH WELD PROCEDURE 8-9

}

62-24-045 i

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Page 2 of 3 MECHANICAL MAINTEMANCE

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JANUARY 1982 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION 1A REACTOR FEED PUMP CORRECTIVE OUTAGE MECIIANICAL LEAKED EXCESS-INSTALLED NEW MECil-MR-0508 81-19 SEAL LEAK IVE AMOUNT ANICAL SEAL ON NORTH OF WATER END OF PUMP LOWER CONTROL ROD PREVENTIVE OUTAGE NA NA PERFORMED PREVENTIVE DRIVE (CRD) NO. 3 MR-0022 81-19 MAINTENANCE AND RESET FRAME TIIERMAL RELIEF VALVE TO 4050 PSIG, ilUNG FOR SPARE GLAND STEAM GENERATOR CORRECTIVE OUTAGE WORN TUBES LEAKAGE INSTALLED NEW STAINLESS MR-0035 81-19 STEEL TUBE BUNDLE 4

ilVA MAIN STEAM ROTO-CORRECTIVE OUTAGE WATER ERODED LEAKED THROUGH, INSTALLED NEW KIT l, PORT PILOT VALVE MR-0041 81-19 NOT ALLOWING AND LAPPED SEATS l

VALVE TO OPER-ATE 4

l LOWER CRD'S FRAMES CORRECTIVE OUTAGE RELIEFS PYDRAUL LEAKED RESET RELIEF VALVES

1. 5 AND #6 MR-0042 81-19 LIFTED THROUGH TO 4050 PSIG 4

LOWER CRD FRAME #22 CORRECTIVE OUTAGE RELIEFS PYDRAUL LEAKED RESET RELIEF VALVE MR-0044 81-19 LIFTED THROUGH TO 4050 PSIG MAIN STEAM ROTOPORT CORRECTIVE OUTAGE LEATHERS WORN LEAKED THROUGH REPLACED WITH CHESTER-ACTUATOR MR-0049 81-19 OUT (DETERIOR-TON U CUP SEALS ATED) la AND 1B ROTOPORT CORRECTIVE OUTAGE LEATHERS LEAKED THROUGH REPLACED WITH CHESTER-SUCTION ACTUATOR MR-0052 81-19 DETERIORATED TON U CUP SEALS MR-0059 MOBILE MONITOR PUMP CORRECTIVE OUTAGE BROKEN VANES WOULD OT PUMP FEPLACED VANES AND MR-0063 81-19 NEW BEARINGS t

Page 3 of 3 MECHANICAL MAINTENANCE JANUARY 1982 LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACi10N LOWER CRD FRAME #6 PREVENTIVE OUTAGE NA NA PERFORMED PREVENTIVE MR-0069 81-19 MAINTENANCE AND CHECKED THERMAL RELIEF LOWER CRD FRAME #13 CORRECTIVE OUTAGE GEAR SLIPPED SYNCHRO INDICA-INSTALLED NEW HYDRAULIC MR-0074 81-19 ON SECONDARY TION INACCt1 RATE MOTOR SEAL AND STAKED TRANSMISSION GEAR IN SECONDARY TRANSMISSION f

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE JANUARY 19b2 At the onset of the January 1982 reporting period, the outage which had commenced December 23, 1981, continued.

Plant electrical systems were checked out and maintenance items completed..

At 0222 on January 22, 1982, the reactor was taken critical.

At 3

0508, a reactor scram occurred from approximately 10

%' power.

The reactor was returned to critical at 1658 and reactor heatup contin-ued.

At 0217 on January 24, the reactor scrammed from 0.1% power due to low recirculation flow, when the IB Forced Circulation Pump tripped.

The reactor was returned to critical at 2048 on January 24.

At 2109 on January 25, the turbine-generator was connected to the DPC grid, but it was removed from the grid at 2200 due to lack of response of the Turbine Governa: Control System Initial Pressure Regulator (IPR).

A cylinder on the newly installed IPR positioner was found not to have been factory preloaded.

The cylinder was loaded and the turbine-generator was resynchronized to the DPC system at 0012 on January 26.

The IPR again did not respond properly and the generator was removed from the grid at 0045.

The generator was reconnected to the DPC system at 0105 and disconnected at 0148.

An air leak was found on the IPR positioner, which had been installed during the outage as part of the PM Program.

An o-ring was replaced and the generator was synchronized to the DPC grid at 0707 on January 26.

The IPR responded properly and a slow escalation commenced.

The plant achieved 70% Reactor Rated Thermal Power (31 MWs-Net) at the end of the January reporting period.

Significant maintenance items performed during the reporting period are indicated on the attached Mecnanical Maintenance and Instrument and Electrical Maintenance listings.

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REFUELING INFORMATION REQ 7 JEST 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-VII) is March 19, 1982.

3.

Scheduled Date for Restart Following Refueling The tentatively scheduled date for subsequent reactor startup is May 1, 1982.

4.

Will Refueling or Resumption of Operation 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 cuestions 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 amendme.nt will be needed for refueling or subsequent resumption of operation.

The Safety Review Conmittee'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, Significant Changes in Fuel Design, New Operating Procedure.

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:

165 Irradiated Fuel Assemblies

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REFUELING INFORMATION REQUEST - (Cont'd) 1.

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

440 Fuel Assemblies 9.

The Projected Date of the Last Refueling that can be Discharged to the Spent Fuel Pool Assuming the Present Licensed Capacity.

1990

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