Text

Monthly Operating Rept for Mar 1980
	ML17318A675
Person / Time
Site:	Cook
Issue date:	04/02/1980
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17318A673	List: ML17318A672; ML17318A675;
References
	NUDOCS 8004150365
	Download: ML17318A675 (15)
	v • d • e

OPERATIC DATAP.EPORT DOCK"-TiO.

DA: "=

COifPL";:-D "- Y T LEPHO.~'=

50-316 ME JL '~PJ 1ett

~~6!M901 OP= ~gTIyG STATUS Oona'td C.

Cook Mal"ch

3. Lic"nsed The....aiPowe. (MYit)t

4. N mepiate Rating (Gross i;f)Ve):

5.

Desi@> Elect&~ Ra-i'Net ibIVr'e):

6. Wi~wmum Dependable Capacity (Gross bfYe):

7..'ifaximum Dependabl Capacity (;i s &fee}:

S. IiChutes Occur in Capa"'.y Rati..y (Items Yamber 1980 3391 1133 Notes 1118 1082 3 Throu~> 7) Sine" Last Report. Give Reasons:

9. Power Level To %which Res -.c!+, IiAny (4 et ~DVe):

IO. Rw~ons For Res-'.ctiora, IfAny:

This 4fonth Yr:to-Dat.

Cumulative

11. Hov s laRepo"Ing P riod IZ. Yumber Oi Houa Reactor Yc'as Critical

13. Re ctor Rese~'e Shutdovwi Hove

14. Hours Gener tor On.Lme

15. Unit R~we Shutdown Ho"<

16. Gross Thecal Enemy Cere.=ted {WIY/H)

17. Cross Elective@

"neroy Generated fief)YH)

18. Yet Eiectrical ~we:~ Cen r"-t ". (.'I'iVH)

19. Unit Servic Factor

20. Uni( AvailabiiiryFactor

1. Unit Capacity Factor (Usin~ i~IDC Yet) 2". Unit Caoacity Factor (Usin~ DER Net)

"3 Unit. orce O:aoe Rat"

.4. Shutdowns Sche"vied 0'e. Hex: 6 lo..ths 728. 4 1 729.8 0

0 726. 1 1 647.1.

0 0

~99 801,060

'. ~7, 80

,212,606 1,698,480 TKm'7.

6

75. 4 96.'1

69. 3 94.5

68. 1 2.4 2.6 (Tpe. Date. and Dv.ation of Each):

12 809.7 0

12 149 0

37,436,986 11,852,890 11,404,329

70. 5

64. 5

63. 4

12. 3 "5. If Shu: Down At End Of Repor; P riod. Es'.imated Date of Sta.", ~ ot

5. Units in Test Sta:us IPrior to Cetnmercial Opera:io..):

Forecast Aen>eved lihlTIA'..iTIALITY IVITIAL ELECTRICITY CO.'INIE...CIAi OP:-:.ATIQ~

VERAGE DAILY UNIT PONER LEVEL~

DOCKET NO; 50 316 UNIT 2

DATE 4-2-80 COMP! ETED 8Y W. T.

Gillett TELEPHONE 616-465-5901 MONTH DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 10 12 13 14 15 16 782 1 023 1 002 1,078 1,088 1,087 1,087 1,089 1,040 1,089 1,090 1,091 1,065 1,080 1,092 17 18 19 20 21 22 23 24 25 26 27 28 29 30 31 1 092 1 079 1 084 1,090 1,088 1,089 1,093 1,093 1,092 1,091 1,091 1,091 1,093 1,090 1,088 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.

UNITSIIUTDO'IUNS AND PO)VER REDUCTIONS REPORT hIONTII March, 1980 DOCKET NO.;~2 DATE 4-8-80 COhlPLETED I)Y TELEPIIONE 616 465-5901

~

l)atc

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III J

II <<

a Q <<Q x gn'-

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Cl Llccn sec Event Itcpoft Jr Cause &. Corrcctivc Action to Pfcv col ltccufIco cc 74 800301 F

17.9 A

3 N.A.

CH VALVOP Reactor/Uni t trip due to extreme 1 ow level in No.

4 steam generator caused by problems.with the feed-water regulating valve for steam generator No. 4.

The Unit was returned to service the same day.

1005 reactor power was reached 800302.

I: Forced S: Scllcdulcd I')/7.7) ltcason:

A E(luipnlcnl FJllufc (ExplJin)

D.hlaintenance or Test C-Rcf)ielintl D I<et,)ilatory Restriction I.Operator Trainii)t, &. License I'xaminatinn F-Adnllnlstfill)Ye G.OpcratlonJI Error (I'.xplJin)

Il.otl)cf(ExpIJnl) hlethod:

I -hlanual 2.htal)ual Scfanl.

3.Auto)natic Scran).

4-Otllcr (Explaul) 4 Exllibit G - Instructions for Preparation ol Data Lntry Sllects for Lice>>sec Event Reporl (LI.'R) File (NUltl:G-OI6 I )

'Lxllibit I

~ Salnc Source

UillTSHUTDOWNS AND POWER REDUC

> S INSTRUCTIONS This report should describe all plant shutdowns during the report period..in addition. it should be the source 'of explan-ation of significant dips in average power levels.

Each signi-ficant reduction in power level (greater than 2'eduction in averaee daily power level for the preceding 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months ) should be noted, even though the unit may not have been shut down completelyl.

For such reductions in power level, the duration should be listed as zero, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should explain.

The Cause and Corrective Action to Prevent Recurrence column should be used to provide any needed explanation to fully describe the circumstances of the outage or.power reduction.

NUMBER.

This column should indicate the sequential num-ber assigned to each shutdown or sienificant reduction in power for that calendar year.

When a shutdown or significant power reduction begins in one report period and ends in another.

an entry should be made for both report periods to be sure Jl shutdowns or significant power reductions are reported.

Until a unit has achieved its first power generation, no num-ber should be assigned to each entry.

DATE.

This column should indicate the date of the start of each shutdown or signiricant power reduction.

Report as year. month. and day.

August i4. 1977 would be reported as 770814.

When a shutdown or sienificant power reduction begins in one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or significant power reductions are reported.

TYPE.

Us "F" or "S" to indicate either "Forced" or ",Sche-duled," respectively, for each shutdown or significant power reduction.

Forced shutdowns include those required to be initiated by no,.later than, the weekend. following discovery of an uif-normal condition.

It is recognized that some judg-ment is required in categorizing shutdowns in this way.

In

general, a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.

DURATION.. Self~xplanatory..

When a shutdown extends beyond the end oi a report period, count only the time to the end ot the report period and pick-up the ensuing down time in the following report periods.

Report duration of outages rounded to the nearest tenth ofan hour to facilitate summation.

The sum of the total outage hours pius the hours the. genera-tor was on line should equal the cross hours in the reporting period.

REASON.

Cateet>rize by letter designation in accordance with the table appearinv. on the repi>rt torm. Ifcategory H must be used. supply briei comments.

METHOD OF SHUTTlNG DOWN THE REACTOR OR REDUCING POWER.

Caleeorize by number designation INole that this difters lrnm the Edison Electric Institute (EEI) definitions ol'Forced Partial Outaee" and

-Sche-duled Partial Outage."

F>>r these tern>>. I:El uses a chance ol'.0 MW as the break pi>int.

F>>r larger pov er reactors. 30 MW is l i>i> small a change ti> warraill <<xplanath>>l.

in accordance with the table appearing on the report form.

Ifcategory 4 lnust be used, supply brief comments.

LICENSEE EVENT REPORT.

Reference the applicable reportable occurrence pertaining to the outage or power reduction.

Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five part designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416l).

This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether vr not a reportable occurrence was involved.) Ifthe outage or power reduction will not result in a reportable occurrence.

the positive indication of this lack of correlation should be noted as not applicable (N/A).

SYSTEM CODE.

The system in which the outage or power reduction originated should be noted by the two digit code of Exhibit G - Instructions for Preparation of Data Entry Sheeis for Licensee Event Report (LER) File (NUREG4161).

Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.

COMPONEiNT CODE.

Select the most appropriate component from Exhibit I - Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG4161).

using the following critieria:

A. Ifa component failed, use the component directly involved.

B.

If not a component failure, use the related component:

e.g..

wrong valve operated through error: list valve as component.

C. If a chain of failures occurs, the first component to mai-function should be'listed.

The sequence of events. includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence colum'n.

Components that do not fit any existing code should be de-

, signated XXXXXX. The code ZZZZZZ should be used for events where a component designation. is not applicable.

CAUSE; &. CORRECTIVE ACTION TO PREVENT RECUR-

,RENCE.

Use the column in,a narrative fashion to amplify or explain the circumstances of the shutdown or power reduction.

The column should include the specific cause for each shut-down or significant power reduction and the immediate and contemplated long term corrective action taken. if appropri-ate.

This column should also be used for a description of the major safety. related corrective maintenance performed during the outaee or power reduction includine an identification of the critical path activity and a report of any sinele release of radioactivity or single radiation exposure speciticaily associ-ated with the outaee which accounts for more than 10 percent of the allowable annual values.

For long textual reports continue narrative on separate paper and ret'eren<<e tile shutdown or power reduction for this ilarfalive

~

UNITSHUTDOWNS AND POWER REDUCTIONS INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition. it should be the source oiexplan-ation oi signiftcant dips in average power Ieveh.

Each sieni ~

."<cant reduction in power I vel (gr ater than 20% reouction in.averaee daiiy power level ior tne preceding 24 houa) should be noted, even though the unit may not have been shut 'down completelyl.

For such reductions in power level, the duration should be listed as z ro, the method of reduction should be listed as 4 (Other), and the Cause and Corrective Action to Prevent Recurrence column should exphin.

The Cause and Corrective Action to Prevent Recurrence coiumn should be used to provide any needed explanation to fully describe the circumstances of the outage or power reduction.

NUMBER.

This column should indicate the sequential num.

ber assiened to each shutdown or signiftcant reduction in power for that calendar year.

When a shutdown or signiftcant power reduction begins in one report period and ends in another.

an entry should be made for both report periods to be sure JI shutdowns or sieniftcant power reductions are reported.

Until a unit has achieved its first power generation, no num-ber should be assiened to each entry.

DATE.

This column should indicate the date of the start of each shutdown or signiftcant power reduction.

Reoort year. month. and day.

Aueust 14. Io77 would be reported as 770814.

When a shutdown or signiftcant power reduction beeinsin one report period and ends in another, an entry should be made for both report periods to be sure all shutdowns or signiftcant power reducuons are reported.

TYPE.

Use "F" or "S" to indicate either "Forced" or "Sche.

duled," respectively, for each shutdown or signlftcant power reduc:ion.

Forced shutdowns include those required to be initiated by no later than the weekend following discovery of an oii-normal condition.

It is recognized that some judg-ment is required in categorizing shutdowns in this way.

In general.

a forced shutdown is one that would not have been completed in the absence of the condition for which corrective action was taken.

DURATION.

Selfwxpianatory.

When a shutdown extends beyond the end oi a report period, count oniy the time to the end oi the report period and pic'p the ensuing down time in the following report periods.

Report duration of outages rounded '.v the nearest tenth ot an hour to faciTitate summation.

The sum of the total outaee hours plus the hours the eenera-tor was on line should equal the cross hours in the reportine period.

REASON.

Categ<)rise by letter designation in accordance with the table appearing on the report t'orm. Ifcateeory H must be used. supply briet comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCINiG POWER.

Cateeorize by number designation IN<ote that this differs t'rom the Edison Electric Institute tEEI) deftnitions ot'Forced Partial Outage" and

-Sche.

duled Partial Outage."

Fiir these tcnns. I:Fl uses

~ change or'.0 MW as the break p<>int.

Fi>r larger pov er reactors. 80 MW is ti<<< small a chance tii warrant cxpianatiiu<.

in accordance with the table appearing on the report fortn.

Ifcategory 4 must be used. supply brief comn:ents.

LICENSEE EVENT REPORT =.

Reference the applicable reportable occurrence pertaining to the outage or power reduction.

Enter the ttrst four parts (event year. sequential report number, occurrence code and report type) of the ftve part designation as described in Item 17 or Instructions ior Preparation of Data Entry Sheets for Licensee Event Report (LER) FUe (NUREC416!).

This information may not be immediateiy evident for all such shutdowns, of course. since further investigation may be reouired to ascertain whether or not a reportable occurrence was involved.) If the outage or power reduction wlII not result in a reportable occurrence.

the positive indication of this lack of correlation should be noted as not applicabie (Yi/A).

SYSTEM CODE.

The system In w'mch the outage or power reduction originated should be noted 'oy the two digit code of Exhibit C - instructions for Preparation oi Data Entry She ts for Licensee Event Report (LER) File (NUREC416l).

Systems that do not fit any existing code should be designa-ted XX. The code ZZ should be used for those events where a system is not applicable.

COMPONE<<<'T CODE.

Select the most appropriat component from Exhibit I - Instructions for Preparation of Data Entry She ts for Licensee Event Report (LER) File (NUREC4161).

using the following critieria:

A. Ifa component failed, use the component directly involved.

B.

If not a component failure, use the related component:

eg..

wrong valve operated through error: list valve as component.

C.

If a chain of failures occurs, the ftrst component to mai-function should be listed. The seauence of events. includ-ing the other components which fail, should be described under the Cause and Corrective Action to Prevent Recur-rence colum'n.

Comoonents that do not fit any existing code snould be de-signated XXXXXX. The code ZZZZZZ should be used For events where a

component desienation is not applicable.

CAUSE 4 CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use the column in a narrative fashion to ampiiiy or explain the circumstanc s of the shutdown or power reduction.

The column should include the specific cause for each shut ~

down or significant power reduction and the immediate and contemplated long term corrective action taken. ifappropri ~

ate.

This column should also be used for a description of the major safety-related corrective maintenance performed durine

'he outaee or power reduction includine an identification of the critical path activity and a report of any sinele release of radioacti<dty vr single radiation exposure specittcaily associ-ated with the outaee which accounts ior more than 10 percent oi the allowaole annual values.

For lone textual reports continue narrative on separate paper and re!'<'.rence tlte shutdown or power reduction for thts narrative.

Doc No.:

Un>

Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 82.

R.

S.

Lease (616) 465-5901 April 9, 1980 1 of 3'3 MONTHLY OPERATING EXPERIENCES -- MARCH, 1980 Hi hl i hts The Unit operated at 100% power the entire reporting period except as detailed in the Sugary.

There was one outage of the Reactor and Turbine Generator Unit during the reporting period.

This is also detailed in the Summary.

Total electrical generation for the month was 801,060 Mwh.

~Sumnar 3/1/80 The Reactor and Unit tripped from 100% power at 0044 hours5.092593e-4 days 0.0122 hours 7.275132e-5 weeks 1.6742e-5 months .,

Turbine Valves were being tested and Turbine Control had been left in manual mode.

This caused greater than normal load deflection.

Level control of No.

4 Steam Generator was sticky and sluggish and did not keep up to the demand.

The actual cause of the trip was lo lo level in No.

4 Steam Generator.

The Reactor was returned to criticality at 1623 hours0.0188 days 0.451 hours 0.00268 weeks 6.175515e-4 months .

The Turbine Gene'rator Unit was paralleled to the system at 1839 hours0.0213 days 0.511 hours 0.00304 weeks 6.997395e-4 months .

3/2/80 The Unit was loaded to 48% power by 2145 hours0.0248 days 0.596 hours 0.00355 weeks 8.161725e-4 months and held at this point for clean up of Steam Generators.

The Unit was loaded to 100% power between the hours of 0320 and 1510.

3/4/80 The North Reheater Coils were isolated at 0925 hours0.0107 days 0.257 hours 0.00153 weeks 3.519625e-4 months .

Cause of isolation was failure of one of the second pass drain controls.

The South. Reheater Coils were removed from service.

All Reheater Coils were returned to service by 1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months .

The "A" string of Low Pressure Heaters were returned to service at 2330 hours0.027 days 0.647 hours 0.00385 weeks 8.86565e-4 months .

This string of heaters had been left out of service from the start-up of 3/1/80, for tube leak repairs in the No.

4 Heater.

4

~ '

II'

Do~ No.:

UnMName:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 82 R.

S.

Lease (616) 465-5901 April 9, 1980 2 ofI3 3/10/80 -- The South Heater Drain Pump tripped at 1055 hours0.0122 days 0.293 hours 0.00174 weeks 4.014275e-4 months due to a,malfunction of the Automatic Discharge Valve.

This started a transient on the Unit which resulted in the other drain pump also tripping and isolation of steam to the Reheater Coils.

Loading of the Unit was reduced to 90/ and stabilized at this point.

Two Heater Drain Pumps were again available for service at 1630 hours0.0189 days 0.453 hours 0.0027 weeks 6.20215e-4 months and the Reheater Coils were returned to service at 1710 hours0.0198 days 0.475 hours 0.00283 weeks 6.50655e-4 months .

The Unit was loaded to 100/

power by 1850 hours0.0214 days 0.514 hours 0.00306 weeks 7.03925e-4 months .

3/12/80 -- The Turbine Driven Auxiliary Feedwater Pump was inoper-able for a 7.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for replacement of the out-board pump bearing.

3/13/80 The Turbine Driven Auxiliary Feedwater Pump was inoper-able for a 6.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for adjustment to the Trip and Throttle Valve.

3/14/80 -- The South Reheater Coils isolated at 1720 hours0.0199 days 0.478 hours 0.00284 weeks 6.5446e-4 months followed by isolation of the North Coils.

This was due to an extreme high alarm on a First Pass Drain Tank.

Unit power was reduced to 95Ã and stabilized at this point.

3/15/80 -- The Reheater Coils were returned to service and the Unit loaded 1005 power by 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months .

The 69/4KV Reserve Off-site Power Source was out of service for a 6.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period:for;preventive o>aintenance.

3/21/80 -- The Turbine Driven Auxiliary Feedwater Pump became inoperable at 1330 hours0.0154 days 0.369 hours 0.0022 weeks 5.06065e-4 months when the Turbine Trip Coil was found to be burned up.

The Trip Coil was removed and the Turbine tested to verify that the mechanical overspeed would still function.

This pump was again declared operable at 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months , 3/22/80.

3/25/80 -- The Turbine Driven Auxiliary Feedwater Pump was in-operable for a 5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to renew the Turbine Trip Coil.

Auxiliary Feedwater Valve FN0-221, was inoperable for a 1.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period when it was found that this valve could not be operated from the Control Room.

The prob-lem was found to be a loose wire in the motor operator of the valve.

/

<<I

%I

Do No.:

50-316 Un~Name:

D.

C.

Cook Unit b'2 Completed By:

R. S.

Lease Telephone:

(616) 465-5901 Date:

April 9, 1980 Page:

3 of 3 Various Condenser Halfs were out of service, one half at a

time, for a total of 51.5 hours5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months during the 'reporting period.

This is for checking and location of tube leaks.

DOCKET NO.

UNIT NAME

'ATE COMPLETED BY TELEPHONE PAGE 50 - 316 D ~

C.

Cook - Unit No.

2 4-8-80 B. A. Svensson 616 465-5901 1 of 3 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1980 M-1 M-2 Motor to pump coupling on radiation monitors Rll and R12 sample pump failed.

Replaced coupling.

Turbine driven auxiliary feedpump outboard pump bearing was running hot.

Replaced bearing and had pump tested.

The motor operated discharge valve from the turbine driven auxiliary feedpump to number 2 steam generator, FM0-221, would not operate from the control room.

Found one armature lead burned off in the connection box.

Installed a new lug and reterminated.

Had valve tested.

CSI-1 CSI-2 C&I-3 CRI-4 Pressurizer pressure bistable NPP-151 was found to be actuating the pressurizer heaters when the pressure reached 2225 psig.

Specifica-tions call for heater actuation at 2210 psig.

The bistable actuation point.was found to be too low and was adjusted to the proper 13.75 ma.

The reset point was also checked and found to be in specification at 15.73 ma.

Pressurizer spray valve NRV-163, loop 3, was leaking in the "automatic" position, causing the pressure to drop.

Investigation disclosed that the zero point on the spray valve po-sitioner had shifted.

The positioner was rezeroed and the valve was verified to be seating properly.

Steam flow/feed flow mismatch alarm and status light were given on steam generator,2, channel ll, steam flow.

The steam flow transmitter was vented and refilled with water and proper output from the transmitter was verified.

Steam generator number 1, feedwater flow regulating valve was operating with valve indication full open, and maximum low deviation on demand.

Steam flow/feed flow and level indications were all normal.

The positioner for feed flow regulator

valve, FRV-210, was recalibrated and the valve stroke was verified.

CLI-5 Radiation monitoring-channel R-ll, containment air particulate monitor filter paper drive system failed.

The filter paper drive assembly, microswitch, take-up reel, supply reel and shafts were replaced.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 316 D.

C.

Cook Unit No.

2 4-8-80 B. A. Svensson 6 6 465-5901 20f3 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1980 The axial power distribution monitoring system would not print the detector being utilized, and would actuate sporadically.

Power supply PS3 was replaced with a spare.

The 1-2 input card and stepping switch were also replaced.

Normal operation of the APDMS was verified.

Main turbine stop valve "C" would not operate in the test mode.

The coil for the stop valve test solenoid valve had failed.

A spare coil was installed and the stop valve test was performed.

Critical control room power inverter "CCRP" frequency would, change periodically.

The frequency on the oscillator board was adjusted to provide synchronous operation.

Radiation monitoring system channel R-19, steam generator blowdown monitor failed.

The high voltage cable and alarm cable were found broken.

The cables were repaired and the channel was returned to normal.

During the performance of a surveillance test, steam generator level bistable 2LB-538A/B, was found to be exceeding specifications.

2LB-538A/B bistable was removed, and a spare bistable was installed and calibrated.

DCR-206, reactor coolant drain tank pump suction isolation valve would not remain open.

A control relay coil and resistor had failed.

The relay and resistor were replaced.

The open and closure time was measured.

The 50 foot wind direction indication on the control room recorder failed to the low end of scale.

The output module failed.

The output module was replaced with a spare, and the calibration was tested.

The 150 foot and 50 foot wind direction indication were checked and indicated the proper direction.

The PLB-1 battery charger would not increase the output voltage when manually switched into the equalize charge mode.

The automatic equalizer timer was removed and cleaned.

Proper operation of the charger was verified prior to returning the charger to service.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 - 316 D.

C.

Cook - Unit No.

2 4-8-80 B. A. Svensson 616 465-5901 3of3 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1980 The 50 foot wind direction recorder indication failed.

The wind direction sensor, secondary

system, had failed.

- The primary wind direction sensor had previously failed.

The primary sensor was replaced and placed into operation.

The turbine driven auxiliary feedpump turbine tripped and would not reset.

The coils on the solenoid for the trip and throttle valve indicated damage and would not pull in the mechanism.

The coils were replaced on the solenoid and the linkage to the,trip and throttle valve was adjusted.

~

'I

ML17318A675

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