ML19344D310

Monthly Operating Rept for Feb 1980

ML19344D310
Person / Time
Site:	La Crosse File:Dairyland Power Cooperative icon.png
Issue date:	03/04/1980
From:	Goodman L DAIRYLAND POWER COOPERATIVE
To:
Shared Package
ML19344D309	List: ML19344D308 ML19344D310
References
NUDOCS 8003110654
Download: ML19344D310 (8)

Text

.

O OPERATING DATA REPORT DOCKET NO.

DATE 03-04-80 COMPLETED BY L.S.GOOG AN TELEPHONE 608-690-2331 OPERATING STATUS N

1. Unit Name: Ta rm"a Am414 m WM-ar hae+ne

2. Reporting Period: 0000, 80-01-62 to 2400, 80-29-02

3. Licensed ThermalPowerIMWtp:

165 65.3

4. Nameplate Rating (Gross MWel:

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 (ltrms Number 3 Through 7)Since List Report. Give Reasons:

9. Power Level To Which Restricted.lf Any (Net MWe1:

10. Reasons For Restricticas,if Any:

This Month Yr. to.Date Cumuistise 696 1440 90,555 iI. Hours in Reporting Period

12. Number Of Hours Reactor Was Critical 638.1 1382.1 59,187.6 0

0 478

13. Reactor Resene Shutdown Hours

14. Hours Generator On-Line 621.5 1365.5 54,370.3

15. Unit Reserve Shutdown Hours 0

0 79

16. Gross Thermal Fnergy Generated (MWH) 84,574 188,577 7,473,357

17. Cross Electncal Energy Generated lMWH) 25,038 55.940 2.255.072

18. Net Electrical Energy Generated (MWH) 23,505 52,647 2,089,987

19. Unit Semce Factor 89.3 94.8 60.0

20. Unit Availability Factor 89.3 94.9 60_1

21. Unit Capacity Factor IUsing MDC Net) 70.4 76.7 48.0

22. Unit Capacity Factor IUsing DER Net) 67.5 73.1 46.1 10.7 5.2 6.3

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months IType. Date and Duration of Each t:

EQUIPMENT INSTALLATION REQUIRED BY NUREG-0578, APRIL 4. 19An. 2-3 WEEKS.

PROJECTED DATE IS BASED ON RECEIPT OF NAMCO SWITcus ON MARCH 10, 1980 AS PER MRC ORDER OF JANUARY 2, 1980.

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

NA

26. Units In Test Status lPrior to Commercial Operation)-

Forecast Achiesed INITIAL CRITICALITY INITIAL ELECTRICITY COMMERCI A L OPER ATION 80081.10[ff'

tJNil SiltilDOWNS AND l'OWER REDUCTIONS DOCKET NO.

50-403 UNIT NAME LACBWR DATE 03-04-80 COMPLETED BY T. n_annnMan RI' PORT MONTil TELEPHONE 608-689-2331 "s

ei 5 u, f;$

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7e'4 1.stemet g -t, Cause & Coeretine D sie 9,

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9 Atison to

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lteport a EL E'

Present Recurrente v

c 80-01 02-01-80 F

74.5 A

3 NA EB ELECON A MOMEETARY LOW VOLTAGE SIGNAL AT THE TURBINE BUILDING 480V 1A MOTOR CONTROL CENTER CAUSED THE SCRAM.

A THOROUGII CHECK OF Q

TIIE PLANT ELECTRICAL SYSTEM WAS g

CONDUCTED, c==,

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l l

2 1

4 I: l'orced Reamn -

Method:

Ediibit G - Inst:uctiims S 5 heilnied A 1 quipinent I ailure ll.xplaini l-Manual for Preparation of Data II Mainterunte oi Test 2 Manual Scrain.

Ento Sheets l'or lxemec C-Refueling 4-Auturnatic Scrain.

Event Report il 1 Ril:tle int RI G.

D.Regulatno Restrittoon 4-Oslier (l.splain )

01611 1 -Opesalor Iranung A I assme i unnnaison.

~

I Adnunisisaine 5

G-Operational 1.sant tI splanal I sinbit I - Sanie Smu.c 19/77) ll Oiher (I splain) i

UNIT SHUIDOhSS AND P0hER REDUCTIONS INSTRUCTIONS This r; port should dessnbe all plant shutdowns durmg the m accordanse with the table appearmg on the report form.

report period. In additmn. it should. ce the source of explan-If category 4 must be used, supply bnef comments i

atwn of sienificant dips m average power lesels. Each sigm.

ticant reduction m power level (greater than 20S reduction LICENSEE EVENT REPORT. Referense the appbwable m' av:ra,:e dady power level for the precedmg 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) reportable occurrence pertammg to the outage or puwer should be noted. even though the umt may not hase been reduction. Enter the first four parts (event year, sequential 1

shut down coinpletely. For such reductions in power level, fePort number, occurrence code and report type) of the five the duration should be hsted as zero,the method of reduction part designation as describcd in item 17 of Instructions tur should be listed as 4 (Other), and the Cause and Corrective Preparation of Data Entry Sheet: for Licensee Event Report Action to Prevent Recurrence column should explain. The (LER) File (NUREG.0161). Tius information may not he Cause and Corrective Actmn to Present Recurrence column immediately evident for all such shutdowns, of course, smse should be used to provide any needed explanation to fully further investigation may be required to ascertam whether or describe the circumstances of the outage or power reduction.

not a reportable occurrence was mvolved.) If the autage or power redustion will not result in a reportable occurrence NUMBER. Tius column should mdreate the sequential num.

the positive indication of this lack of correlation should be ber assigned to each shutdown or significant redxtion in power noted as not applicable (N/A).

for that calendar year. When a shutdown or sigmficant power reduction begins m one report period and ends m another.

SYSTEM CODE. The system in which. tie outage or power an entry should be made for both report renods to be sure re uctmn originated sho' uld be noted b? the two digit code of all shutdowns or sigmfacant powcr reductions are reported.

Exhibit G. Instructions for Preparatioa of Data Entry Sheets Until a unit has achieved its first power generation. no num.

t r Licensee Event Report (LER) File (NU1.LG41611.

ber should be assigr.ed to each entry.

Systems that do not fit any existing code should be destgr.a-ted XX. The code ZZ should be used for those events where DATE. This column should indicate the date of the start a system is not applicable.

of each shutdown or sigmficant power reduction. Report as year. month and day. August 14.1977 would be reported COMPONENT CODE. Select the most appropnate sumponent as 70514. When a shutdown or significant power reduet:on from Exhibit I instructions for Preparation of Data Entry begmsin one report period and ends m another. an entry should Sheets for Licensee Event Report (LER) Fde tNCREG4toI).

be made for both report periods to be sure all shutdowns usme the followmg entieri or sigmfiesnt power reductions are reported.

TYPE. Use "F" or "S" to mdicate either " Forced" or " Sche-duled." respectively. for each shutdown or sigmticant power B.

If not a component fadure, use the related component-i reduction. Forced shutdowns melude those required to be e.g.

wrong valve operated t!..augh error: list sabe a im: ated by no later than the weekend follonng discovery component.

of an of f. normal cu< '; tion. It is recogmzed that some judg.

ment is reqmred m categorizmg shutdowns in tius way. In C.

If a cham of fadures occurs. the first component to mai.

general..i forced shutdown is one that would not hase been function should be hsted. The sequence of events.melud.

completed in the absence of the condition for which corrective ing the other components which fail, should be desertbed action was taken.

under the Cause and Corrective Action to Present Recur.

rence column.

DURATION. Self. explanatory. When a shutdown extends beyond the end of a report penod. count only the time to the Components that do not fit any existmg code should be de.

end of the report penod and pick up the ensumg down time signated XXXXXX. The code ZZZZZZ should be used for m the following report periods. Report duration of outages evems where a component designation is not appheable.

rounded to the nearest tenth ot an hour to iasihtate summation.

The sum er' the totJi outage hours pius the hours the genera.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR.

for was on hne should equal the eron hours m the reportmg RENCE. U3e the column in a narrative fastuon to amphiy or explain the circumstances of the shutdown or power reductien.

The column should include the speettic eause for each shut.

REASON

( aiceon/e m icuei demnanon in.iscordance

"" "', oenttieant power reducti n and the immediate and

"U"

"' ' # EE P"'

with the thle appeanng on the repob tonn. If category H aR.

us column should also be used for a description of the mu a be used. supply boet sommentt maior safety.relatrd corrective mamtenance performed durme ME1 HOD OF SHUTTING DOhN THE REACTOR OR outan or power reduction including an identification at t

REDUCING PO%ER. Cameonte by number designatmo the entical path Jetmty and a report of any smgle release et radmastivn> or smale radianon exposure specifically assoc -

INote that tius ditters from the i diwn I testne Institute awd with the outage which accounts for more than 10 persent (LLll derimoons or " Forced Partial Outace" and " Sche.

of the allowable annual values duled Paitta! Outage? I m these et m i I l uscs hange et For long testual reports contmue narrative or. separate paper

.Id MM Ja the breJi immt Ie

• la' ge. pows reJctors.10 M%

Jthj rererefise the shutdown or power reduition tot thb is I* *

• snlJIi J sliJilge fe d war t Jh! g vptJ'1Jitou n a r ra g gy D*'PB

1. N 9'y 9

4 AD I" '"

e AVERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-Ano UNIT N

DATE 03-04-80 COMPLETED BY L.S.GO N N TELEPHONE 608-689-2331 MONTH _ FEBRUARY 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Neti IMWe-Net) 2 39 I

,7 2

0 39 gg 0

3 i,

39 14 39 20 5

29 39 21 38 39 6

22 39 39 7

33 39 39 a

2.

39 9

25 39 39 10

s 39 11 39 27 39 12 39

s 39 33 39 39 2,

14 39 30 39 15 3,

39 16 INSTRUCTIONS On this format list the average dady unit power level in MWe Net for each day in the reporting month. Compute to the nearest whole megaw.itt.

(9/77) l

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE FEBRUARY 1980 At the onset of the February reporting period, power generation was continuing at 85% Reactor Rated Thermal Power (39 MWe-Net).

This operating power level has been scheduled to extend core life to stretch optimum production until refueling becomes necessary.

At 0200 on February 1, 1980, a signal indicating low voltage at the Turbine Building 480V Motor Control Center lA was momentarily received.

This signal caused the reactor to scram automatically.

The plant electrical system was thoroghly checked.

Although the cause of the undervoltage could not be determined, vibration was thought to have contributed to contact action.

The reactor was returned to critical at 1157 on February 3rd and the turbine generator was synch-ronized to the DPC grid at 0430 on February 4th.

Power escalation continued until February 6th when 85% Reactor Rated Thermal Power (39 MWe-Net) was reached.

Power generation continued at the 85%

level throughout the remainder of the reporting period.

On February 4, 1980, the Nuclear Regulatory Commission issued Amendment No. 19 to LACBWR's Provisional Operating License which extended the maximum average fuel exposure during this cycle (No. 6) from 15000 MWD /MTU to 15,600 MND/MTU.

With the authorization of extended operation, the limited refueling outage formerly scheduled for early February 1980 was postponed.

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

FEBRUARY 1980 INSTRUMENT AND ELECTRICAL MAINTENANCE LER OR NATURE OF OUTAGE MALFUNCTION EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION i

CONTROL ROD DRIVE CORRECTIVE OUTAGE DEFECTIVE ALARM LAMP REPLACED PRESSURE SWITCH (CRD) 18 MR 2976 80-01 SWITCH WOULD NOT CLEAR CONTROL ROD DRIVE CORRECTIVE OUTAGE BROKEN PRESSURE ALARM SETPOINT REPLACED PRESSURE SWITCH (CRD) 3 MR 2982 80-01 TUBE NOT CORRECT NUCLEAR INSTRUMENTA-CORRECTIVE NA OSCILLATOR FRE-TEST FREQUENCY ADJUSTED OSCILLATOR TION MR 2977 QUENCY NOT LOW MR 2979 CORRECT NUCLEAR INST 11UMENTA-PREVENTIVE NA TESTS DUE COMPLETED TESTS COMPLETED TECHNICAL TION SPECIFICATION TESTS N-5 THROUGH N-9 2300 VOLT SWITCHGEAR CORRECTIVE OUTAGE WORN PART BREAKER WOULD REPAIRED AM9 ADJUSTED MR 2973 80-01 NOT CLOSE SHIM STOP MR 2975 CONTROL AIR DRYER CORRECTIVE NA LOOSE BOLTS DRYER VALVE REPAIRED STUCK VALVE MR 2985 STUCK RECOMBINER UNIT TEMP-CORRECTIVE NA DEFECTIVE ALARM WOULD NOT REPLACED ALARM CARD ERATURE ALARM MR 2986 CAPACITOR RESET 1A DIESEL ROOM HEATER CORRECTIVE NA DEFECTIVE TIME HEATER INOPER-REPLACED TIME DELAY MR 2917 DELAY RELAY ABLE UNIT 1B CIRCULATING WATER CORRECTIVE NA FROZEN SENSOR INCORRECT PRES-THAWED FROZEN LINE PUMP MR 2887 LINE SURE INDICATION FIRE DETECTION SYSTEM PREVENTIVE NA TESTS DUE COMPLETED TESTS COMPLETED FIRE DETECTOR l

AND BATTERY TESTS SAFETY SYSTEM PREVENTIVE NA TESTS DUE COMPLETED TESTS COMPLETED SAFETY SYSTEM CH.

1, 2, AND I

WATER LE'!EL # 3 TESTS FIRE DETECTION SYSTEM CORRECTTVE NA CONTAMINATED FALSE ALARM CLEANED DETECTOR MR 2981 FIRE DE2ECTOR 1 of 2 I

i FEBRUARY 1980 INSTRUMENT AND ELECTRICAL MAINTENAN[2, LER OR NATURE OF OUTAGE MALFUNCRON EQUIPMENT MAINTENANCE NUMBER CAUSE RESULT CORRECTIVE ACTION RADIATION MONITORING PREVENTIVE NA TESTS DUE COMPLETED TESTS COMPLETED RADIATION MONITOR TESTING SECURITY SYSTEM CORRECTIVE NA LOOSE CIRCUIT FALSE ALARM REPAIRED CIRCUIT FRONT DOOR.

MR 2989 BOARD BOARD MR 2998 SECURITY SYSTEM CORRECTIVE NA LOOSE CIRCUIT INOPERATIVE RECONNECTED CIRCUIT CRIB HOUSE MR 3001 BOARD BOARD SECURITY SYSTEM CORRECTIVE NA RELAY INOPER-FALSE ALARM REPAIRED ALARM CARD CONTAINMENT DOOR MR 3003 ABLE FUEL OIL STORAGE LEVEL CORRECTIVE NA AIR PUMP DE-INCORRECT REPLACED AIR PUMP GAUGE MR 2995 FECTIVE INDICATION POWER DISTRIBUTION WEL FACILITY NA NEW EQUIPMENT INSTALLED INSTALLED WELDING WELDING OUTLET CHANGE REQUIRED OUTLET OUTLET ON REACTOR 74-80-1 CONTAINMENT BUILDING MR 3007 701' LEVEL 1

i i

6 l

2 Of 2

=

FEBRUARY 1980 t.u:c11ArnrAT, MAINTENANCE LER OR flATURE OF OUTAM

- - -MALFUNCT10h l

EQUIPitEtiT MAltlTLilAtlCE f.of tf.f R CAUSE RESULT CORRECTIVE ACT!0Ti

' LOWER CRD FRAME #5, CORRECTIVE OUTAGE COMMON DRIVE FALSE PRIMARY RESTAKED GEAR TO POSITION #5, CHANGED MR 2984 80-01 UEAR FOR SERVO POSITION INDI-SHAFT.

PERFORMED OUT WITH FRAME #20.

MR 2972 TRANSMITTER CATION PREVENTIVE MAINTEN-LIMIT SWITCH ANCE CHECKS AND CAME UNSTAKED STORED FOR SPARE, FROM SHAFT.

VALVE NO. 52-25-003 CORRECTIVE NA "O"

RING WORN LEAKED REPLACED "O"

N2 TO SEAL INJECT MR 2974 RING AND SEAT H O LEVEL GLASS CORRECTIVE NA BROKEN SIGHT WATER AND STEAM REPLACED ALL MICA, 2

MR 2969 GLASS LEAKAGE, CAUSING GLASS AND PACKING ISOLATION OF GASKETS; TORQUED TO SIGHT GLASS 35 FT. LBS.

GLAND STEAM GENERATOR CORRECTIVE NA BLOWN GASKET LEAKED TEMPORARY REPAIR BY MR 2999 FURMANITE INCORPORATED.

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