ML17326A783

Monthly Operating Rept for Oct 1980

ML17326A783
Person / Time
Site:	Cook
Issue date:	11/04/1980
From:	Gillett W INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17326A782	List: ML17326A781 ML17326A783
References
NUDOCS 8011180657
Download: ML17326A783 (11)

Text

OPFK<711C DATARFZORT DOCK"-TaiO.

DATE CO~fPL~M EY TZI coHONE 50-316

~1-ett

- ~901 OPERATLIG S iATUS Oonald October

1. Unit Namei L Reporting Period:

S. Lic used The.~ Povsc (MYft}t

4. Nameplate Rang (Gross iaaf>Ve}t S. Design E!~MRuing (Net KO'ie)t

6. 5hximunr Dependable Capacity (Gross MÃe)r

7. 5faxuaum Dep~&leQp&y(Net M"Ic)t 1980 3391 1133 1100 1082 Nocc

8. Ef Changes Occr in Capac:~(Rt's (it's Numb= 3 Throg~

gi Since Last Repor Give Reasonst

\\

9.

P owe." L~ei To Mu&Rasa='a~, lfAny (Niet hD'r'e):

10. R~oas For ~ctions, lf'Anyr This Month Yr.<o-Dat=

CumuL" ive 24,840 7,320 0

0 6,068. 6 16,570. 2 1 414 143 19 906 496 52 130 76 456,040 6,457,370 16 611 780 15,996,383 439 846 6,228,971

74. 4

82. 9 8.

69.

77. 4

68. 4 1] ]

6 3

• • Corrected to NRC outa e

rint

11. Houw ln Repormg Penod

,745

~P

13. Re" ctor R~~e Shutdown Ho~,

!4. Hours Generator On-Lhie.

1S. UnitR~~e Shutdown Hoim.

16. Gross Thecal En=~ Genemt&(i')

17. Gross Pe~cd Eae~ Gen~t<

(< f>VH)

13. Net H~mlwc~ Generat~~

{iVsviTa}

19. Unit Servic Factor

20. UritAi~oifityFactor 2I. Unit Capably'actor {Usiag li!QC Net}

~. Unit Forced Outage Rate

42. 4

4. Shutdowns Scnduled Over Nec 6 ~fon!.".s (Type. Date. and Duction of Each):

• -1000 MWHT due to error in A ril 1980 re ort

a. lfShat Doivn At,Fnd Of Report peiod. Estimated Date oi Stamp:

. 'S. Units ln Test Status.f Poor, to Cemmen.".al Op

. tionl:

Fo~t Achieve fihfTfAL CRfTlCALJTY lNlTlAL ELECT'? 1C1TY CO: 1:ifFRClAi OPER'.i TfON "ao6es7 fQraT)

s

AVERAGE DAILY UNIT POWER. LEVEL DOCKET O.~

I UNIT 2

DATE 11-4-80 COMPLETED BY W. T.

Gillett TELEPHONE 616-465-5901 MONTH OCTOBER 1980 DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 10 12 13 15 16 1

57 1057 1063 1055 1059 1056 1053 861 858 1064 1065 1063 1065 17 18 19 20 21 22 23 25 26 27 28 29 30 31 1003 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.

UNITSIIUTI)ONtNS ANI)PO)VER REI)UCTIONS REI'ORThIONTII October, 1980 l)OCKETNO 50 - 316 UNITNAhlF D.C.

Cook Unit 2 COh(PLETEI) IlY TELEPIIONE 616 465-5901 PAGE 1 of 2 N((.

Date

.- L hx A~

VII U< a

~ MI Llccoscc Event Rcporl rr O~

() 0 Eu O

Cause h. Corrc<<live A<<lion to Prcvcnt Rc<<urrcIIcc 86 801011 87 801 012 A

.4g N.A.

N.A.

zz zz zzzzzz zzzzzz Reactor power reduced to 55K to re-move east main feedpump turbine from service to check feedpump turbine condenser for tube leaks.

Two tubes were plugged.

Reactor power returned to lOOK the same day.

Reactor power reduced to 55K to re-move the east main feedpump turbine from service to check feedpump tur-bine condenser for tube leaks.

One leaky tube was plugged.

Reactor power returned to 100K the same day.

88 801017 A

N.A.

zz zzzzzz Reactor power reduced to 55K to re-move east main feedpump turbine from service to check feedpump turbine condenser for tube leaks.

Four tubes were plugged.

Reactor power returned to 1005 801018.

I': For<<c(i-S: Salle(laic(I

(<i/77)

Reas(ul:

A-E<luipmcnl Failure (Explain) ll.h(aintcn:o(ce or Test C-Rcfoelio(,

D-RCI,olatory Rcslri<<lluo I'.Operator 'I'rainiot, 8c License Examination F-A lmioislralivc C Operational L'Ir((r(I'.xpiaio)

II.OII(cr(lixplain) 3 hlethod:

I Manual 2 Manual Sera<n.

3 Autontalic Scr<on.

Q.Otllcf (Explain)

Exl(ibil C< - Inslroclions r>>f Prcparallon or D~lla Itotry SI(ccts fo< l.iccnsec Evcol Rcp rl (I.I!R) I'il (NURI C-OI 6l )

5

'Exl(ibil I

~ S(ooc Sour<<c

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

In addition. it should be the source of explan-ation or 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 <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 completeiyl.

For such reductions in power level, the duration should be listed as zero, thc 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 Rccurrencc 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 reductionin power for that calendar year.

When a shutdown or signiricant 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 sianiftcant power reductions are reported.

Until a unit has achieved its first power generation, no 'num-ber shouid bc assigned to each entry.

DATE.

This column should indicate the date of the start of each shutdown or significant power reducuon.

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 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 corrective acuon was taken.

DURATION.

Seif~xplanatory.

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

Report duratibn of outages rounded to the nearest tenth ot an hour to facilitate summation.

Thc sum of the total outage hours plus the hours the genera-tor was on line should equal the gross hours in the reporting perio.

REASON.

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

METHOD OF SHUTTlNG DOWN THE REACTOR OR REDUCING POWER.

Categorize by numher designation INote that this differs i'rom the Edison Electric institute tEEI) definitions of -Forced Partial Outage-and

-Sche-duled Partial Outage."

For these tern>>. FEI uses a cliange oi'0 MW as the break p)int.

For larger power reactors. ~0 MW is uiii smail a change to warrant explanation.

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 frst four parts (event year. sequential report number, occurrence code and report type) oi 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 inforination 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 reportabie occurrence.

the positive indication of this lack of corr lation 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 Licensee Event Report (LER) File (NUREG4161).

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

COMPONENT CODE.

Seiect the most appropriate component I'rom Exhibit I - Instructions for Preparation of Data Entry Sheets for Liccnsce Event Report (LER) File (NUREG4161).

using the followingcritieria:

A. Ifa component failed, use thc 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 coiumn.

Components that do not fit any existing code should bc de.

signated XXXXXX.,The.code ZZZZZZ should be used for events where a

component designation is not applicable.

CAUSE 4 CORRECTIVE ACTION TO PREVEÃI'ECUR-RENCE.

Use the column in a narrative fashion to ampiify 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 contempiated long term correcuve action taken. ifappropri-ate.

This column should also be used for a description of the major safety-reiatcd corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single release oi radioa<<timtI or single radiation exposure spe<<itically 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 and ret'erence tiie shutdown or power reduction iui tii>>

ilaffJtlvc.

UNITSIIUTDO'ÃNS AND PO)VER REDUCTIONS REI'ORT hlONTII 0ctober')OCKETNO.

UNITNAME DATE COhlPLETED IN TELEPIlONE PAGE 50 - 316 11-12-80 616 465-5901 2 of 2 2

~

~

~

'o.

Date rshx A

F' 3rJ fV'~

e

~

g J Q

x gL U~ a

~ V)

Cl Liccliscc Event

~

Rcpi)ft Jr El CJ Q

D Et O

CJ Caiisc &. Cilrrcclivc Actiinl to Prcvcllt Rccilrrclicc 89 801018 316 A

3 N.A.

HA GENERA Unit trip.

Cause of trip was main generator neutral ground relay actua-tion.

The ground fault was -located in one of the generator stator bars.

Repairs are presently in progress.

The Unit remained out of service at the end of the month.

I r: Focus S: Sclicilulci)

Rcasilit:

A-I:Iiuipntcnt Failure (Explai>>)

I).hlallitcnaoce oi Tesl C-Rc fuclioI, D Rcitulatoly Restriction E.Opciat ir Trliinint,& Licciis Exaolination I'llnllolslllltivc G Opcratioiial I:iror(I'.xplaiii)

I I Oilier (Iixplaiii) 3 hlcthud:

I.hlailoal 2 hlaoual Scraiil.

3-Auloolalic Scraol.

4.0tlu!r (ExplJIII) 4 Exllibit G - Inst ructioos for PrcpafJtloo ilfData LiltrySllccts for l.iccoscc Event Rcpilrt (I.ER) File INURI!(i-OI6l) 5 I.xiijbjt I - Saioc Siulrcc

UNITSHUTDOWNS AND POWER RE IONS

~ C 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 (@cater than 20% reduction in average 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 completelyl.

For such reductions in power level, the duration should be listed as zero, the method of reducuon 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 provid~ 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 shouid be assigned to each entry.

DATE.

This column should indicate the date of the start of each shutdown or sigruficant 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. reductions are reported. --

TYPE.. Usc "F" or "S" to indicate either "Forced" or "Sche-duled." respecuvely, for each shutdown or significant power reduction.

Forced shutdowns inciude 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 absc;ncc of the condition for which corrective action was taken.

DURATION.

Self~xplanatory.

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

Report duratibn 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 equai the gross hours in thc reporting period.

REASON.

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

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation 1Noie that this dift'ers t'rom the Edison Eleciric Institute tEEI) definitions ot'Forced Partial Outage" and

-Sche.

dulcd Partial Outage."

Fair these tern>>. f;El uses a change oi'0 MW as the break point.

For larger puNer reactors. ~0 MW is ici~i small a change to warrant explanation.

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 paris (event year. sequential report number, occ rrence 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 (NUREG416}).

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 correlation should be noted as not applicable (N/A).

SYSTFM CODE.

The system in which the outage or power reduction originated should bc noted by the two digit code ot 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 bc, used for those events where a system is not applicable.

COMPONENT CODE.

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

using the followingcritieria:

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

B. If not a component failure, usc the related component:

eg..

wrong valve operated through error: list valve as component.

C. If a chain of failures occurs, the first component to mai-funcuon 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'8'ORRECTIVE ACTION TO PREVFNT RECUR-RENCE.

Use the column in a narrative fashion to ampiify 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 release ot radioactivity ur single radiation exposure specitically associ-ated with the outage which accounts for more than 10 percent of the allowable annual values.

For long textual reports continue narrative on separate paper and reference the shutdown or power reduction t'or ibis ilaffative

ket No.:

it Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 0'2 C.

E. Murphy (616) 465-5901 November 10, 1980 lof 2 MONTHLY OPERATING ACTIVITIES -- October, 1980 The Unit operated at 100/ power at the start of this reporting period and ended the peri'od in Mode'5.

The Unit experienced a trip from 1005 power when the Main Generator became grounded.

Ground protection relays oper-ated removing the Unit from service.

The details are in the Summary.

Total electrical generation for the month was 456,040 mwh.

10/Ol/80 - MRV-242, one of the Steam Dump Valves for the II'4 Steam Generator Stop Valve was removed from service, for a period of 2.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> to repair leaks.

10/02/80 - AB Diesel Generator was removed from service, for a period of 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> to change oil in the Turbo Charger.

10/07/80 - The Containment Dew Point Recorder (MR-50) was removed from service for a period of 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />, to replace a cable.

10/11/80 - Unit loading was reduced to 55K power over a 2.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> ramp starting at 0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />, to remove the East Main Feed pump from service.

This was for checking and repairs of a Condenser leak.

The East Main Feed pump was returned to service and the Unit reloaded to 100/ over a

7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ramp starting at 1522.

10/12/80 - Unit loading was again reduced to 55K power over a

1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> ramp, to remove the East Main Feed pump from service.

This was to plug a leaking Condenser tube.

The East Main Feed pump was returned to service and the Unit reloaded to 100/ over a

8 hour9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> ramp starting at Z055.

10/17/80 - Unit, loading was again reduced to 554 power over a

1.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> ramp starting at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />, to remove the East Main Feed pump from service for plugging of Condenser" tube leaks.

ket No.:

it Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 C.

E. Murphy (616) 465-5901 November 10, 1980 20f2 Summar cont.

10/18/80 - The East Main Feed pump was returned to service and the Unit reloaded to 100Ã power over a 7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> ramp, starting at 0215.

The Unit tripped from 100K power at 2057, a Generator Neutral Ground Relay Actuation was the cause of the trip.

A Ground has been identified within the gener-ator and repairs are underway at this time.

10/19/80 - Cooldown and degassing of the Reactor Coolant System was started at 2115, for an investigation of a tube leak in ¹21 Steam Generator.

10/20/80 10/21/80 10/23/80 10/29/80-10/31/80 Unit entered Mode 4 at 0200.

Unit entered Mode 5 at 0200.

Reactor Coolant System at ', loop operation at 0938.

¹21 Steam Generator was pressurized to 900 lbs. with Nitrogen to check for tube leak.

There was no visable leakage at this pressure.

Eddy Current Testing was performed and it was decided to plug 6 tubes.

"AB" Emergency Diesel was returned to service at 1350 and successfully tested to the Load Bank after Modifi-cations were made for RFC 2039.

DOCKET NO.

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

C.

Cook - Unit No.

2 11-12-80 B. A. Svensson 616 465-5901 1 of 1

MAJOR SAFETY-RELATED MAINTENANCE

OCTOBER, 1980 M-1 No.

1 steam generator stop valves dump valves, MRV-211, MRV-241 and MRV-242 were leaking by.

Replaced the seat ring and gaskets.

Had valves tested.

M-2 C&I-1 C&I-2 C&I-3 C&I-4 A flow instrument flange in the RHR system between valves IRV-310 and ICM-311 was leaking.

Replaced the flange gasket.

Main turbine stop valve B and control valve C would not test as required.

The limit switch on stop valve B was inspected.

A bushing in the limit switch was replaced.

The proximity switch for stop valve B had vibrated loose.

The proximity switch was remounted.

The limit switch arm on control valve C was sticking.

The switch was disassembled and the mechanism was lubricated.

A retest of the valves verified operability.

Main turbine stop valve C would not test to the closed position.

The coil of the control valve test solenoid failed and was re-placed.

The shaft and bushing on stop valve A, open limit switch, also required replacement.

CD Diesel 60 psi reducing valve to the turbo charger failed to the open position, producing 100 psi pressure, opening the relief valve.

The valve was removed and a spare was installed and adjusted to provide 60 psi air supply.

Axial power distribution monitor system, power level actuation bistable No.

1 trip setpoint was found to be 885 reactor

power, while bistable No.

2 actuated at 925 reactor power.

The input voltage required to trip bistable 1 was recorded as.3.81 volts with the required setpoint at 3.83 V DC.

The bistable was re-calibrated to trip at the correct voltage and power level.