Text

Monthly Operating Rept for Aug 1980
	ML17319A593
Person / Time
Site:	Cook
Issue date:	09/05/1980
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML17319A592	List: ML17319A590; ML17319A593;
References
	NUDOCS 8009160277
	Download: ML17319A593 (14)
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OPFKCTLNG DATARK~ORT DOCK:"7 iX'O.

DATE CO~IPL~ED BY T"L""PHOEBE 50-315 ME tt j~M01

-. -- -:.-0?:"RArLING 5iA:US D. C.

Cook

l. Unit riaaret Reporting Pe=.ou.

Au ust S. Ltcauet The.&?awe: (alt)c

4. Naaeptate Raring (Grass i~OVe):

S. Design EI~MR=mg (Net MNe):

6. h~ua Depeadabt= Capacity (Gross 5Nc)r i.~~Tnum Dc@="~M=C"peaty (Net ht'Ve)t S. IfChanges Occur ia Czpac.".g R"ctngs (lt"ms Yuwbcr S Unit 1

1980 3250 089 1054 080 1044 i fores Through 7) Sine= Las Repoc:. Give,Rcasonst

-9.- Pawe&v&ci"AirtRes-.=~, IfAny (-.'ict SDVe):

-IO: Rmons'Par ReaMcas, IfAny:

This Month Yr.aa-Dat=

Cu~tauve

'- 'IX HattWIn-R.<<cede'Period

" l~'. '; fur,.b R Of'H'o&a $bnctor Yfas C;:uM "I~. Rc"c:ar Ramie Sht..dovva Houw

~~. HoQzs GRID. IDYOa=Lbre

~ Unit;RaavrShucctmvn Hot~.

b5. Gnss~tezmM. ~ Cene.=t& PWH) f7; Gross'HK~t ~~ Gcn=rac& (i'tbYH) ltt'. r~ecHPwef Kc"'~Gener"t~ ( t)VII)

-. U~rSerrtr~Vacttn..

"t. U~fc~iFactar'(Usia~ lIOC'Yet)

~ UrtrCl5rc+W tar(Usta~ D R Yet)

Un~a~

"4. Shutdo~xs Scheduled Over Yce, 6 itoatbs 644.4 0

574. 6 3 852.3 0

463 0

1,501,561 0

11,620,492 100,686 797

>>. OM4 77.2 77.2 64.

5'4.5 75.4 66.2 10.6 7.2 4.4 t r ype. Date. and Du.=cion ot'Each):

R ti Stcam.>i a<Of Re"ort P boa. Bcirrated D te ai Stamp:

~

S. Units ta Test-S~:us tPrior to Cew-...what Op.. ciort:

Achieved.

tYtTIALCRtTiCALITY tftiiAL "-LeCTR!Cl r Y CO: t.'t "RCtAt QP"=R:~ Tt04 8009'180 @ Pf

0/ERAGE DAILY UNIT POWER LEVEL DOCKET NO.

50-'15 '

UNIT DATE 9-5-80 COMPLETED BY

,W. T. Gillett TELEPHONE 616-465-5901 MONTH AUGUST 1980 DAY AVERAGE DAILY POWER LEVEL (MWE-Net) 200 391 391 DAY 17 18 19 20 21 22 23 24 25 AVERAGE DAILY POWER LEVEL (MWe-Net) 427 851 969 979 989 993 996 999 998 10 15 498 634 508 781 939 530 26 27 28 29 30 31 998 992 995 994 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.

REPOR fhlONTII 980 UNITSIIUTDOIVNSAND PO)VER REDUCTIONS DOCKET NO.

UNITNAME DATE COhlPLETED DY TELEPIIONF.

PAGE 50 315 D. C.

Cook Unit gl 616 465-59 1

1 of 2 No.

160 l)atc 800530 S

134.6 BLC

'J U< s

~ II) a Lice>>scc Event Rcp))rt 4 N.A.

>>>~

o ~

Q O

E~

0 Zz Zzzzzz Cause 4, Cl)frcctivc Acti)>>l to Prcvcnt Rccurrc>>cc The unit was removed for Cycle IV-V refueling outage on 800530.

Following completion of the outage and low power'hysics testing the unit was returned to service on 800806 at 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months .

The total length of the outage was 1624.1 hours1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months .

~;

161 800806 7.1 3

N.A.

ZZ ZZZZZZ Turbine/Reactor trip due to extreme high level in right moisture separator shell during startup due to an alterna drain valve being closed.

162 800807 1.0 B

N.A.

Zz Zzzzzz Unit removed from service to perform turbine overspeed trip testing.

Unit returned to service and the power escalation test program commenced.

I". I orccd S: Schedule)i Rcaso>>:

A-Equipmcnt Failure (Explain) ll.hlal>>tc>>I>>lcc of 1 csf C-Rcfueli>>I, D Rct,ulatory Restriction I.'.Operator Training> 8I Lice>>sc Iixa>>ll>>allo>>

F-Adminislra Iivc G Opcratio>>al Error (I'.xplai>>)

II Other (Expla>>l) hlethod:

I -hlanoal 2.hlanual Scraln.

3-Auto>>la tie Scr;I>>l.

4-Other (Explai>>)

Exhibit G - Instr>>etio>>s for Preparatio>> ol'ata L>>try Sheets lor Lice>>scc Event Rcport (LI!R) File (NURIIG-OI 6I )

'L'xhibit I - Sal>>c Source

UNITSHUTDOWNS AND POWER REDU NS 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 207o reduction in average daUy 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 Usted 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 significant 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 all 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'he 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 significant 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 reducuons are reported.

TYPE.

Use "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 oif-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 ot a report period, count only the time to the end of the report period arid pic'p 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 plus the hours the genera-tor was on line should equal the gross hours in the reporting period.

REASON.

Categorize by letter designation in accordance with the table appearing on the report form. Ifcategory H must be used. supply briei comments.

METHOD. OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INoie that this differs t'rom the Edison Electric Institute IEEI) definitions of -Forced Partial Outage" and

-Sche.

duied Partial Outage."

Fi>r these tern>>. EEI uses a change of

0!>IW as the break point.

Fi>r larger power reactors. 30 MW is ii>>'mall a ihange ti> warrant cxplanaiii>>i.

in accordance with the table appearing on the report form.

Ifcategory 4 must. 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 (NUREG4161).

This information may not be immediately evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or not a reportable occurrence was involved.) If the 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 Sheets 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.

COi>>IPONENT CODE.

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

using the followingcritieria:

A.'fa component failed, use the component directly involved.

B.

If, not a component failure, use the related component:

e.g.,

wrong valve operated through'rror: list valve as component.

C. If a chain of failures occurs, the first component to mai-func'tion 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 column.

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. ifappropri ~

ate.

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

For long textual reports continue narrative on separate paper anJ ret'erence tlie shutdown or power reduction for this llarfative.

REPORT hIONTII~180 UNITSIIUTDO)VNS AND PO)VER REDVCTIONS DOCKET NO.

VNITNAh(E DATE COh(PLETED IlY TELEPIIONE PAGE B. A. Sv n s

n 61 1

2of 2 l)alc rI IA sJ Q ll~'J jp

~4

~ C/)

Licensee Event Rcport 4 CJ~

O U

E ~

O Cause & CorrcI.tive Action lo Pfcvcnl Rccurfcncc 163 800816 164 800816 6.2 2.2 G

3 H

1 N.A.

N.A.

ZZ ZZ ZZZZZZ ZZZZZZ Reactor/Turbine trip from 93% power.

Trip was due to a false steam flow/

feedwater flow mismatch coincident wit low level in No.

3 steam generator caused by operator error during instru ment surveillance testing.

Tripped turbine-generator manually after 1.2 hours2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months of operation due to high vibration on No.

3 turbine bearin Unit returned to service and power increased to 92K.

165 800831 18.3 3

0-020/03-L-O EO ZZZZZZ Reactor/Turbine trip due to failure of inverter for vital A.C. instrument bus Channel IV.

Unit returned to service and power increased to 95K.

I". Forced S: Sclledulcd (I)/77)

Reason:

A-EI)uiplncnl Failure (Explain)

II-h(allltcnance or Test C-Refueling D-Regulatory Restriction E.Opcralof Training & Lice>>sc I:xanlinalion F-Administrative G.Opcralio>>al Error ((explain)

I I Olllcr (Explain) 3 hiethod:

I Manual 2 Manual Scram.

3.Autonlatic Scr;Inl.

4-Olller (Explain) 4 Exllibil G - Instructions for Preparation ol'ala Lnlry SIIccls for Llecnsec Event Report (LI!R) File (NURliG.

Ol 6I )

Lxlnbil I - SaIne Source

UNITSHUTDOWNS AND POWER REDU NS 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 20% reduction in average 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 completely>.

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 significant 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 a11 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 signiiicant power reduction.

Report as year. month. and day.

August i4. 1977 would be reported as 770814.

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 all shutdowns or signiricant power reducuons are reported.

TYPE.

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

du!ed," respectively, for each shutdown or significant power reduction.

Forced shutdowns include those required to be initiated by no later than. the weekerid following.discovery of an oif-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.

Seif~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 oi the total outage hours plus the-.hours the genera-tor was on line should equal the gross hours in the reporting period.

REASON.

Categt>rize by letter designation in accordance with the table appearing on the report form. Ifcategory H must he used. supply briei'comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INote that this differs i'rom the Edison Electric institute (EEI) definitions ot

-Forced Partial Outage" and

-Sche-duled Partial Outage."

Fi>r these term~.

F.F I uses a el>ange oi'.0 MW as the break point.

F<<r larger power reactors. 30 MW is iii'ismall a change ti> warrant explanatii>>i.

in accordance with the table appearing on the report form.

Ifcategory 4 must 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 (NUREG4161).

This information may not be immediateiy evident for all such shutdowns, of course, since further investigation may be required to ascertain whether or 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).

SYSTFM CODE.

The systein in which the outage or power reduction originated should be noted by the two digit <<ode of Exhibit G - Instructions for Preparation of Data Entry Sheets 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.

CO>SIPONENT 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

, comoonent.

C.

If a cham 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 column.

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 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 during the outage or power reduction including an identification of the critical path activity and a report of any single reiease ot'adioactivity or single radiation exposure speciiically associ-ated with the outage which accounts for more than 10 percen(

of the allowable annual values.

For long textual reports continue narrative on separate naper and ret'erence the shutdown or power reduciiun i'>>> this liarfJtlve.

Do t No.:

U Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit 0'1 R. S.

Lease (616) 465-5901 "1

September 5,

1980 lof3 MONTHLY OPERATING ACTIVITIES -- AUGUST, 1980 Highlights During the reporting period, this Unit,was returned to service from it's fourth Refueling Outage.

This is detailed in the Summary.

Gross electrical generation for the month was 484,090 mwh.

8/1/80 Heatup was initiated and the Reactor plant entered Mode 6 at 0644 hours0.00745 days 0.179 hours 0.00106 weeks 2.45042e-4 months .

The East Main Feed Pump Turbine was overspeed trip tested.

8/2/80 The Reactor plant entered Mode 3 at 0310 hours0.00359 days 0.0861 hours 5.125661e-4 weeks 1.17955e-4 months .

Full temperature and pressure were obtained at 0955 hours0.0111 days 0.265 hours 0.00158 weeks 3.633775e-4 months .

8/3/80 Following completion of rod position indication checks and adjustments and control rod drop testing dilution for criticality was initiated at 2105 hours0.0244 days 0.585 hours 0.00348 weeks 8.009525e-4 months .

8/4/80

-- Criticality was achieved at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

8/6/80

-- Following completion of Low Power Physics Testing the Reactor plant entered Mode 1 at 1235 hours0.0143 days 0.343 hours 0.00204 weeks 4.699175e-4 months .

The Main Turbine was rolled at 1237 hours0.0143 days 0.344 hours 0.00205 weeks 4.706785e-4 months .

The generator was paralleled to the system at 1435 hours0.0166 days 0.399 hours 0.00237 weeks 5.460175e-4 months .

The Unit tripped from approximately 20/ power at 1523 hours0.0176 days 0.423 hours 0.00252 weeks 5.795015e-4 months .

Cause of trip was extreme high level in the right Moisture Separator.

Reactor was returned to critical at 2055 hours0.0238 days 0.571 hours 0.0034 weeks 7.819275e-4 months .

The Main Turbine was rolled at 2205 hours0.0255 days 0.613 hours 0.00365 weeks 8.390025e-4 months .

The generator was paralleled to the system at 2228 hours0.0258 days 0.619 hours 0.00368 weeks 8.47754e-4 months and loaded to 30Ã power by 2400 hours0.0278 days 0.667 hours 0.00397 weeks 9.132e-4 months .

I

Docket No.:

U~ Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit ¹1 R. S.

Lease (616) 465-5901 September 5,

1980 2of3 8/7/80 8/8/80 The generator unit was removed from service at 0420 hours0.00486 days 0.117 hours 6.944444e-4 weeks 1.5981e-4 months for overspeed testing.

The Unit was again paralleled to the system at 0518 hours0.006 days 0.144 hours 8.564815e-4 weeks 1.97099e-4 months and loaded to 30/ power by 0900 hours0.0104 days 0.25 hours 0.00149 weeks 3.4245e-4 months .

The Unit was loaded to 48% power over a

5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 1910 hours0.0221 days 0.531 hours 0.00316 weeks 7.26755e-4 months .

The West Main Feed Pump Turbine was overspeed tested.

'/10/80

-- The Unit was loaded to 68% power over a 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months ramp starting at 1025 hours0.0119 days 0.285 hours 0.00169 weeks 3.900125e-4 months .

8/12/80 8/13/80 8/14/80 1

8/15/80

, 8/16/80--

The Unit was loaded to 78% power over a

7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months ramp starting at 0725 hours0.00839 days 0.201 hours 0.0012 weeks 2.758625e-4 months .

The West Motor Driven Auxiliary Feed Pump was inoperable for an 11 hour1.273148e-4 days 0.00306 hours 1.818783e-5 weeks 4.1855e-6 months period to repair a

leaking Discharge Check Valve.

The Unit was loaded to 88% power over a 4 hour4.62963e-5 days 0.00111 hours 6.613757e-6 weeks 1.522e-6 months ramp starting at 2238 hours0.0259 days 0.622 hours 0.0037 weeks 8.51559e-4 months .

The Unit was loaded to 91% power over a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 1825 hours0.0211 days 0.507 hours 0.00302 weeks 6.944125e-4 months .

The Unit was loaded to 93% power over a

5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 2354 hours0.0272 days 0.654 hours 0.00389 weeks 8.95697e-4 months .

The Unit tripped from 93/'ower at 1340 hours0.0155 days 0.372 hours 0.00222 weeks 5.0987e-4 months .

The cause of trip was Steam Flow Feed Flow mis-match coincident with low level on No.

3 Steam Generator.

Instruments Surveillance was being performed at the time and proper Control Channels for this generator had not been selected.

The Reactor was returned to criticality at 1825 hours0.0211 days 0.507 hours 0.00302 weeks 6.944125e-4 months .

The Unit was rolled and paralleled to the system at 1950 hours0.0226 days 0.542 hours 0.00322 weeks 7.41975e-4 months .

The Turbine was unloaded and removed from service at 2105,hours due to excessive bearing vibration.

The Reactor remained critical at this time.

Following lubricating oil temperature adjustment, the Unit was rerolled and paralleled to the system at 2315 hours0.0268 days 0.643 hours 0.00383 weeks 8.808575e-4 months .

0 I

1

- ~

Do~t No.:

U~ Name:

Completed By:

Telephone:

Date:

Page:

50-315 D.

C.

Cook Unit 81 R.

S.

Lease (616) 465-5901 September 5,

1980 3 of 3 8/17/80 The Unit was loaded to 48Ã power by 0505.hours.

Loading was held at this point due to an Indicated Quadrant power tilt.

The Unit was loaded to 92K power over a

16 hour1.851852e-4 days 0.00444 hours 2.645503e-5 weeks 6.088e-6 months ramp starting at 2310 hours0.0267 days 0.642 hours 0.00382 weeks 8.78955e-4 months .

8/19/80 -- The Unit was loaded to 93K power at 1332 hours0.0154 days 0.37 hours 0.0022 weeks 5.06826e-4 months .

8/20/80 -- The Unit was loaded to 94Ã power at 2155 hours0.0249 days 0.599 hours 0.00356 weeks 8.199775e-4 months .

8/21/80 -'- The AB Emergency Diesel Generator was inoperable for a 39.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period starting at 0930 hours0.0108 days 0.258 hours 0.00154 weeks 3.53865e-4 months for flushing and renewal of control fluid in the governor.

8/23/80 -- Power was increased to 95% at 1456 hours0.0169 days 0.404 hours 0.00241 weeks 5.54008e-4 months .

8/25/80--

I 8/27/80--

8/29/80 The AB Emergency Diesel Generator was -inoperable for a 9.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for repair of a fuel oil leak and replacement of an exhaust thermocouple.

The West Containment Spray Pump was inoperable for a

12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period to repair a leaking weld.

IJ The AB Diesel Emergency Generator was inoperable for a 7.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to check the engine timing.

The West Residual Heat Removal Pump was inoperable for a 3.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period to clean the air screens on the motor.

8/31/80 The Reactor tripped from 95Ã power at 0447.

Cause of trip was loss of power on vital Instrument Bus 84.

With the loss of this Bus Safety Injection and Steam Line Isolation were also initiated.

Safety Injection was terminated 12 minutes later.

The loss of the Instrument Bus coincided with a lightning strike in the close vicinity of the plant.

The Reactor was returned to critical at 2139 hours0.0248 days 0.594 hours 0.00354 weeks 8.138895e-4 months .

The Unit was rolled and paralleled to the system at 2308 hours0.0267 days 0.641 hours 0.00382 weeks 8.78194e-4 months .

The Unit was loaded to 458 power by 0355 hours0.00411 days 0.0986 hours 5.869709e-4 weeks 1.350775e-4 months 9-1-80.

Loading was held at this point due to an indicated Quadrant power tilt.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE 50 315 D.

C.

Cook - Unit No.

1 9-12-80

~B..

Svensson 616 465-5901 1 of 1

MAJOR SAFETY-RELATED MAINTENANCE AUGUST, 1980 M-1 M-2 The east centrifugal charging pump outboard mechanical seal was leaking.

Disassembled pump, rebuilt -seal, reassembled and tested.

The emergency leakoff line check valve for the west motor driven auxiliary feedpump was leaking by.

Lapped the seat and replaced the disc.

C8(I-1 Incore detector flex drive.Unit 'F'orward reverse contactor would not pick up at voltages less than 100.

The contactor was replaced and the detector'rive was checked for operation in both forward and reverse modes.

CSI-2 CRI-3 CSI-4 Resistance to voltage converters on aT/TAVE Loops 2, 3, and 4 were out of specification.

These loops were recalibrated.

Lower Containment Pressure

Channel, PPP-301, indicated -0.5 PSIG.

Channels PPP-300, 302 and 303 were indicating zero.

The indicator for Channel, PPP-301, was found to be reading low and was recal-ibrated.

The values for all channels then were cross-checked and are in agreement.

Wind Speed

Recorder, SG-19, failed.

A new chart drive motor was installed.

ML17319A593

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