ML17317B100

Monthly Operating Rept for Mar 1979

ML17317B100
Person / Time
Site:	Cook
Issue date:	04/05/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317B101	List: ML17317B100
References
MOR-790331-1, NUDOCS 7904180261
Download: ML17317B100 (15)

Text

AVccDCE DAILYUNITPpbER I:-VEL

.DOCZ=-T~O '0-315 I%IT 1

DAT:

4-5-79 COMPLEi D BY W.T.. Gi1 lett T-r "~HONE Mome March 1979 DAY AVEUCE DAILYPONr'ER L= rr EL (MNe.lei) 104 901 21 843 1044 1042 1043 1043 1040 19 50 24 55 A~ ER ACE DAII.Yrrpb eg L~r:r (MWe.bet I 1044 1043 1047 1044 1044 1044 689 309 10 l5 16 1041 1043 1044 1041 1042 1043

.1045

'r5 50 818 1032

'038 1038 1038

l. ISTRU~iONS Ofr:.mls seri.zr

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OPERATIC DATAREPORT DOCI cT qi()

50-315

. DiTE ~~4-COMPLETED 8Y ~~ii31ett TELEPHONE MM&3901 OPERATINC STATUS I

UnitName'Onald C.

COOk 1

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Cross MÃe):

S. Design Eiectri&R"ting (Net hiWe):

6. bfaximum Dependable Capacity (Gross MWe)t T..'Ifaximum Dep ndable Ca pac".'ty (N t MWe):

3 250 1 089 1 080 1,044 Notes S. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Cive Reasons:

9. Power Level To Which Restr.:ctM, IfAny (Net L~IWe):

10. Reasons For Restrictions, IfAny:

This Month Yr.-to-Date Cumulative II. Hours In Reporting Period IZ. Number Of Hours Reactor Was C.":tical

13. Re"ctor Reserve Shutdown Houa

14. Hours Cenemtor On-Lne IS. Unit Reserve Shutdown Hots

16. Gross Thermal Energy Gene.=ted (MWH)

17. Gross Efecuicaf Energy Generated (Llf>VH)

18. Net Electrical Energy Generated (IDVH) 19: Unit Sexvic Factor ZO. Unit AvailabilityFactor ZI. Unit Capacity Factor (Using MDC Net)

~. Unit Capacity Factor (Using DER Net)

~D. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months 744 2,160 37 44.

683. 9 679.5 0

, 39,30 686,060 2,083.1 29 294.8 0

463 0

321 77,868,114

,58, 80

.6,530,323

91. 3

96. 1 96.1 9.

79. 5

88. 3 92.8 70.2

87. 4

91. 9

64. 3 ITvpe. Date. and Duction of Each ):

2 092 287 24,429 464

'S. IfShut Down At End Of Report Period. Estimated Date of Startup:

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'5. Units ln Test Status IPrior to Commercial Operation):

Fore st Achieved INITIAL CRITICALITY Ii'4ITIAL ELECTRICITY CO,'I!lfERCIAL OPERA 7IOi'4 fu/I i )

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UNITSIIUTI)OWNS ANI)POIVER REI)UCTIONS REPORT hIONTII hla<<h UNITNAhIE D.C.Cook-Unit 1

I)ATE 4-13-79 COMPLETEI) IIY B.A. Svensson TELEPIIONE 61 6 465-5901 N(>.

I)ate C

C$

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(I) g CI LI(.cosec Event Rcport Jf Ew EI 0 I/I wG E)~

g 4I r) Kl E~

O Cr Cause Ec Coflccllvc A<<lion lo Prevent Rc<<urrcoce 146 790302 F

147 790323 F

24.7 39.8 A

1 79-015/03L-0 79-019/03L-0 ZZ ZZZZZZ EB Zzzzzz Unit removed from service due to

'failure of the rupture disc on the pressurizer relief tank.

The pres-sure surge caused all ice condenser inlet doors to indicate open.

The unit was returned to service 790303 and loaded to 1005 790304.

Reactor/Turbine trip caused by near simultaneous failure of two vital instrument bus inverters.

The in-verter failures also caused inadver-tent actuation of the safety injec-tion systems and steam line isola-tion.

Repairs were made and unit returned to service on 790325 and lOOX power reached on 790326.

I': Forced S: Scheduled I')177)

Reason:

A.E(lolpnlcnt Failure (FxplJill)

I).hlaioico'ulcc or Test C.RC fuclloi, f).RCI,ula tory Reslri<<lion Ii.Operator Trainh>I',8c License Exao>Illa!Ion F-Ad olinisl ra Iive G.Opc('alluoal Lffof (Explahl)

II Olhcf (Expla>ol hlclhod:

I 4laoual 2 hianual Sera>n.

3.Autonlatic Scralo.

4 Olhcf (ExplJ>o) 4 Exhibit G - Inslru<<lions fof Prep(IfJlh)o ol I)ata I>otry Shcels for l.iccosec fvcol Rcp()rl (I.I!R) File (NIIIII!G

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Lxhlblt I SJol(. hoor(.<

UNITSHUTDOWNS AND POWER REDUCTIONS

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0 INSTRUCTIONS This report should describe all plant shutdowns during the report period.

In addition. it should be the source of exphn-ation of significant dips in average power levels.

Each signi ~

ficant reduction in power level (greater than 20%a reduction in averaae daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) should be noted, even thouah 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 Correcuve 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 il 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 significant po~er reduction.

Report as year. month, and day.

Auaust i4. 1977 would be reported as 770S14.

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 sianificant 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 off-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.

Seifwxplanatory.

When a shutdown extends beyond the end of a report period, count only the time io the end oi the r port period and 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. Ifcateaory H must be used. supply briefcomments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation INoie that ibis diifers from the Edison Electric Institute (EEI) definitions oi'Forced Partial Outaae" and

-Sche-duled Partial Outage.-

For these tcrni~. I:EI uses a change or'0 MW as the break point.

For larger power reactors.30MW is n~'i small a change i<> warrant cxplanatiou.

in accordance with the table appearing on the report torm.

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, occurrenc 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 (NUREC4161).

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.) Ifthe outage or power reduction will not result in a reportable occurrence.

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

SYSTFM 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 Lic'ensee Event Report (LER) File (NUREG4161).

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

COhiPONENT 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 followingcritieriai 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 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 inciude 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 outaae or power reduction including an identification of the critical path acti~ity and a report of any single release of radioactivity or sinale radiation exposure speciiicaliy 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 und ret'crcnce the shutdown or power reduction ioi tl!i>

ilaffatlvc.

(9/7

UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO.

REPORT hION'fll 9

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Llccoscc I!vent Rcport 4 C<

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p CJ Cause &. (.))rr).).ttvc A<<tilol t))

Prcvcnt Rccorrcocc 148 790326 0

4 N/A ZZ ZZZZZZ Reactor power was reduced to 52Ã to permit removal of the west main feed pump from service.

Problem was corrected without removing pump from service and power returned to 100K 790327.

I I': Fur<<cd S: Scl)cdulcd Rcas()n:

A-Erluipmcnt Failure (Explai>>)

I)-hlalotct)ance oi Tesl C-Rcfuelioi, D-Rein)latory Rcslricliuo I:.Operator Iralnlnt', & Liccosc I:xan)loall))n F-Adolinistlativc Ci Opcratlunal LI'rl)f (Explain)

II.Olllcr(Explain) 3 hlcth<)d:

I.Manual 2 hianual Scraln.

3-Auto)oat Ic Scnln).

4.0t llcr (Explain)

Exllibit G - lostru<<lions for Preparati)o) ol Data Entry Sllccts for Licensee Event Rcp rl (LER) Flic INURI.:0-OI 6l )

'Exllibit I - Saloc S))ulcc

> IT SHUTDOWNS AND POWER REDUCTION INSTRUCTIONS This report should describe all plant, shutdowns during the report period.

In addition. it should be the source ofexplan-ation of significant dips in average power levels.

Each signi ~

ficant reduction in power level (greater than 2¹ reduction in averaee daily power level for the preceding 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />) should be noted, even though the unit may not have been shut down completely 1.

For such reductions in power levei, 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 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 assigned to each shutdov:n or sienificant reduction in power for that calendar year.

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

Report as year. month, and day.

Aueust i4. 1977 would be reported as 770814.

When a shutdown or significant power reduct'.on 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.

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 off.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 correcuve 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 plus the hours the genera-tor was on line should equal the cross hours in the reporting period.

REASON.

Categorize by letter >Iesignation in accordance with the table appearing vn th>> report torm. Ifcategory H must be used. supply brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR

~

REDUCING POWER.

Categorize by number desienation INote that this differs from the Edison Electric institute (EEI) definitions ot'Forced Partial Outaee-and

-Sche.

duied Partial Outage.-

F>>r these tonus. I.EI uses a chance of

.0 MW as the break point.

Fi>r Iar>'.er puver reactors.SOMW is i>>'> small a chance ti> warrant explanaiion.

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 desienation 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.) Ifthe outage or power reduction will not result in a reportable occurrence.

the positive indication of this hck of correlation shou/d be noted as not appliuble (N>tA).

SYSTFM 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 Lic'ensee Event Report (LER) File (NUREG4161).

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

CO>MPONENT 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 followingcritieria:

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 ofevents. 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 4 CORRECTIVE ACTION TO PREYED'ECUR-RENCE.

Use the coiumn 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 sienificant power reduction and the immediate and contemplated lone 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 outaee or power reduction includine an identifiution of the critical path ac:ivity and a report of any sinele release of radioactivity or sineie radiation exposur~ speciiiully associ-ated with the outaee which accounts for more than 10 percent oi the allowable annual values..

For lone textual reports cominue narrative on separate paper an>I reterence tlie shutdown or power reduction for thi>

narrative.

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

50-315 D.

C.

Cook Unit 81 R.

S.

Lease (616) 465-5901 April 12, 1979 MONTHLY OPERATING EXPERIENCES MARCH, 1979 Hi hl i hts This Unit has operated at full Reactor power the entire period except as noted in the summary.

Total, electrical generation for the month was.711,210 Mwh.

Summar 03/02/79 -- Loading was started down at 2011 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.651855e-4 months <br /> and the Unit was removed from service at 2109 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.024745e-4 months <br />.

Reason for "the outage was a rupture disc on the.Pressurizer.

Relief Tank had ruptured causing all Ice Condenser Doors to indicate open.

The Ice Condenser Doors were closed at 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br />.

Cause of the ruptured diso to fail was a feed and bleed procedure which was in process to reduce tank temperature.

03/03/79 Both ruptured discs were replaced on the Pressurizer Relief Tank and the Reactor returned to criticality at 1906 hours0.0221 days <br />0.529 hours <br />0.00315 weeks <br />7.25233e-4 months <br />.

The Unit was placed in parallel with the system at 2155 hours0.0249 days <br />0.599 hours <br />0.00356 weeks <br />8.199775e-4 months <br /> and loaded to 1005 power by 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br /> 3/4/79.

There was a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> hold at 47K power due to an indicated quadrant Power Tilt.

03/23/79 -- At 1549 hours0.0179 days <br />0.43 hours <br />0.00256 weeks <br />5.893945e-4 months <br /> the inverters of two vital instrument buses failed near simultaneously.

This resulted in a Reactor trip, Turbine trip and Safety Injection.

The failure was capacitators within the inverters.

The "AB" station battery was under equalizing charge at this time and failure was attributed to excessive voltage.

03/25/79 -- Immediate Unit restart was not possible because the Boron Injection Tank had been injected into the system during the safety injection and it required time to return this to Chemical Specifications.

The'eactor was returned to criticality at 0559 hours0.00647 days <br />0.155 hours <br />9.242725e-4 weeks <br />2.126995e-4 months <br /> and the Unit paralleled to the system at 0734 hours0.0085 days <br />0.204 hours <br />0.00121 weeks <br />2.79287e-4 months <br />.

The Unit was loaded to 100$ power by 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> 3/26/79.

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-315 D. C.

Cook Unit ¹1 R.

S.

Lease (616) 465-5901 April 12, 1979 Two (2) 03/26/79 -- Reactor Power was reduced to 52% power starting down at 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> to remove the West Main Feed Pump from service.

Reason was there was noise -in the front end of the Turbine Drive.

Cause was found to be the motor driven auxiliary pump and the shaft driven oil pump running together opposite one another.

Stopping of power reduction was attempted at 60Ã power, but this core being so near the end of life the xenon transient reduced power to 52K before it could be turned around.

Power was returned to 100% by 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br /> 3/27/79.

0 I

0

DOCKET NO.

50 - 315 UNIT NAME D.

C.

Cook - Unit No.

1 DATE 4-13-79 COMPLETED BY B. A. Svensson TELEPHONE 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1979 ESW-113 and ESW-114, 1CD diesel essential service supply check valves leaked by.

.The discs were replaced.

Retest was satis-factory.

ESW-111 and ESW-112, lAB diesel essential service supply check valves leaked by.

The discs were replaced.

Retest was satis-factory.

North waste gas compressor would not develop discharge pressure.

Replaced compressor suction valve disc (RRY-378).

Retest was sat-isfactory.

The rod position indicator for F-6 indicated greater than 12 steps from the demand position.

The panel indicator was found drifting.

The LVDT secondary coil voltage measurement indicated a constant signal.

The signal conditioning module was removed and the cards edge connector was cleaned.

Following reinstallation, the panel meter indication returned to the correct value.

The control bank D rods began to withdraw at maximum stepping speed when the rod control system was placed into the automatic mode.

The problem was determined to be module 1TY-412P supplying the auctioneered Tavg signal to the system.

The module was removed from the control loop and required replacement of R-2 gain poten-tiometer.

The control system was returned to service following the repair of the module.'PI-253, turbine driven auxiliary feedpump discharge pressure in-dication indicated 300 psig lower than the local test gauge.

The transmitter was found to be out of calibration.

The transmitters calibration was performed and the control room indication was verified.

IFA-250, boron injection tank recirculation flow alarm, indicated a flow rate of 9 gpm and the alarm was received in the control room.

The setpoint of IFA-250 was found to actuate at 11 gpm.

The set-point of the alarm was adjusted to actuate at 8 gpm as required.

Grid I inverter failed.

Capacitor C2, fuse FU-2 and the oscillator circuit board were replaced.

Correct operation of the inverter was verified and the inverter was returned to service.

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DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE MAJOR SAFETY-RELATED MAINTENANCE MARCH, 1979 50 - 315 D. C.

Cook - Unit No. 1, 4-13-79 B. A. Svensson 616 465-590 'rid II inverter failed.

Capacitor C2 had failed and ruptured.

Capacitor C2, fuses FU-1 and FU-2, silicon controlled rectifiers SCR-3 and SCR-4, and diodes D4 'and 05 were replaced.

Operation of the inverter was verified and the unit returned to service.

HARV-112, CVCS Letdown isolation valve, would not open.

The circuit problem was traced to a HFA relay which would not operate when energized.

The relay would operate and remain energized.

The relay would operate and remain energized when manually assisted.

The 'relay will be replaced during the Unit 1 Refueling Outage.