ML17317A747

Monthly Oper Rept for Oct 1978

ML17317A747
Person / Time
Site:	Cook
Issue date:	11/01/1978
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317A746	List: ML17317A745 ML17317A747
References
NUDOCS 7811210438
Download: ML17317A747 (11)

Text

AVERAGE DAILYUNITPOWER LEVEL DOCKET NO UNlT DATE COMPLETED BY T LEPHONE October 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe-Ner 1 I

864 1,013 DAY 'VERAGE DAILYPOWER LEVEL

(.'>IWe..'>>er )

906 906 IO I3 l5 16 987 909 918 888 900 907 902 0

906 I9 20

'>5 26 27 2S

'>9 30 31 914 901 904 904 903 612 480 902 890.

5 900 894 886 888 INSTRUCTIONS On this format. !ist th average daily unit p>>iver lese! tn Mme-Net for each day in the repurtina >n>>nth. C>>moute tv the nearest v'hole m ga~vat t.

vsxtia00 5<

9-

{<)r77)

'1

OPERATING STATUS Dcnald C. Cook 2

1. Unit Name:

2. Reporting Period:

3. Licensed Thermal Power (MWt):

4. Nameplate Rating (Gross MWe):

5. Design Eiectricai R"ting (Net MWe):

7. ifaximum Dependable Capacity {Net lfWe):

OPERATING DATAREPORT Notes DOCKET NO 6

DATE TELEPHONE ~~ 5901 S. IfChanges Occur in Capacity Ratings (Items Number 3 Through 7) Since Last Report. Give Reasons:

9. Power Level To Which Restricted, IfAny (Net ilIWe):

10. Reasons For Restrictions, IfAny:

This Month Yr.-to.Date Cumuhtive 7,296 7,296 745 4 131.7 3 660.0 ',660.0 9,780,817 2 915 450 2,915g450 2 783 98

79. 3

79. 3 79.3 64.4 64.4 9.4

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 734. 1

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 730. 1

15. Unit Reserve Shutdown Hours 0

~ Ã

17. Gross Electrical Fnergy Generated (MWH)

19. Unit Serrice Factor

30. Unit AvailabilityFactor

21. Unit Capacity Factor (Using MDC Net) 82

32. Unit Capacity Factor (Using DER Net)

80. 7

~D. Unit Forced Outage Rate

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

"5. IfShut Down At End Of Report Period. Estimated Date of Startup:

~

26. Units In Test Status IPrior to Commercial Operation):

INITIALCRITICALITY INITIALELECTRICITY COh&IERCIAL OPERATION Forecast 3/1/78

~31~S78 MUzs.

Achieved 3/10/78 3~22 ~

~71 78 I'>j77)

UNI'fSIIUTI)01VNS ANI)PO)VEII IIEI)UCTIONS gEI OgT hIONTII October, 1 978 l)OCKET NO.

ITlaaa gphIPLETEI) IN B.A. Svensson TELEPIIONF 616 465-5901 No.

l)ale

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~ rlt g Llccosce Ilvcot l(cpult 4 V~

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Cause h, Corlc<<live Actiott lo Plevct'll Ilccurrcllec 38 781024 F

14.9 78-080/03L-0 IA IHSTRU Unit removed from service due to problems with reactor protection system Train A test circuit.

Problem found to be test circuit boards.

F: Forces S: Scltedulc(l lteaso>>:

A hlulplncnt Failure ( I:xplalo) 1).hlai>>tcoancc or lest

('-IIcfocli>>g I) )tet,nlatory llestrictiuo I: Opcralor Ilatntug Ec Llccose Ilxaonolalluo I'rlolinislralive (i.Opcratlullal Ellor (lixplaio)

I I Olllcr(Explain) hlelhod:

I-hlaoual 2 hlanual Scraln.

3.Aututoatic Scrawl.

4.0lllcf(Explaul) 4 Exllibil G - lost nlctions for Prepalatiint ol l)ala I.otry Sbcets 1 or Ll<<eosee Evcot Report (I.I.'R) File (NUIII!(l-0161) l.xhibit I - Salnc Sintrcc

UilITSHUTDOWNS Ai<D 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 leveh.

Each signi ~

ficant reduction in power level (gr ater than "0% reduction in averaae daily power levei for the prec ding '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 tnay not have been shut down completelyi.

For such reducuons 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 circumstanc s of the outage or power reduction.

NUMBER.

This column should indicate the sequential num-ber assigned to each shutdown orsianiiicant reductionin 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 oeriods to be sure Jl shutdowns or signiticant power reductions are reported.

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

DATE.

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

Report as year. month. and day.

Auaust 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 signiticant power reductions are reported.

TYPE.

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

duled." respectively, ior each shutdown or significant power reduction.

Forced shutdowns include those required to be initiaied by no later than the. weekend following discovery oi an oif-normal condition.

It is recognized that some judg-tnent 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 correcrive action was taken.

DURATION.

Selfwxplanatoty.

When a shutdown extends beyond the end of a report period. count only the time to the end ot the report 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 ot the total outage hours plus the hours the aenera-tor was on line shouid equal the gross hours in the reporting period.

REASON.

Categorize by letter designation in accordance with the table appearing on the report t'orm. Ifcategory H must be used. suppiy brief comments.

METHOD OF SHIJTTING DOWN THE REACTOR OR REDUCING POWER.

Caieaorize by number desianation I'.4oie ihat this differs irom the Edison Electric Institute fEEI) deimitions oi -Forced Partial Outage" and

-Sche-duled Partial Outaitc."

F<<r these tcrnis. EEl uses

~ cliange of

0 ifW as the break point.

For hrger poN er reactors.

SO ifW is i>>'< small a change to warrant exnianaiio<i.

in accordance with the table apoearing on the report form.

Ifcategory 4 must be used, suppiy brief comments.

LICENSEE EVENT REPORT =.

Reference the applicable reportable occurrence pertaining to th.

outage or power reduction.

Enter the first four parts (event year. sequential report number, occurrence code and report type) of the five patt designation as described in Item 17 of Instructions for Preparation of Data Entry Sheets for Licensee Event Report (LER) File (NUREG416I).

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

SYSTEM CODE.

The system in which the ouuge or power reduction originated should be noted by the two dblit code oi Exhibit G

~ Instructions for Preparation oi 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<iIPONENT 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 thecomponentdirectlyinvolved.

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-funcuon should be listed. The sequence of events. includ-ing the other components which faii. should be described under the Cause and Corrective Action to Prevent Recur-rence column.

Comoonents that do not fit any existing code should be de.

signated XXXXXX. The code ZZZZZZ should be used ior events wnere a

component desianation is not applicable.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

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

The column should include the soecific cause for each shut-down or significant power reduction and the irt mediate and contemplated long term corrective action taken. ifappropri ~

ate.

This column should also be used for a description of the major safety-related corrective maintenanc periotmed during the outaae or power reduction including an identification oi the critical path ac:ivity and a report of any single reiease oi radioactivity or single radiation exposure speciiicaily associ-ated with the ouuae which accounts ior more than 10 oerceni oi the allowable annual values.

For long textual reports continue narrative on separate paper nd reference tlie shutdown or power r!duinivn for this ilaffative.

Doc ke o.:

Unit Name:

Date:

Completed By:

Telephone:

50-316 D.

C.

Cook Unit 82 November 14, 1978 R.

S. Keith (616) 465-5901 OPERATING EXPERIENCE -- OCTOBER, 1978 Hi hli hts Unit 2 was on line 734 hours0.0085 days <br />0.204 hours <br />0.00121 weeks <br />2.79287e-4 months <br /> and 4 minutes out of a possible 745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />.

Summar 10/01/78 The Unit entered this reporting period operating at 60/

power with adjustments being made to the steam pressure transmitter for the Main Feed Pump Turbine.

Repairs were completed and a return to 1005 power was started at 0507 hours0.00587 days <br />0.141 hours <br />8.382936e-4 weeks <br />1.929135e-4 months <br />.

'10/02/78 -- The 'Turbine Driven Auxiliary'Feed Pump was out o'f service

'for 3 hours3.472222e-5 days <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> to repair a steam leak.

10/03/78 The East CTS Pump was declared inoperable at 0630 because of a broken valve stem on IM0-212.

10/04/78--

10/06/78 The Southeast coils of the Moisture Separator Reheater were removed from service because of a suspected tube leak.

Unit load was reduced to 90'A at 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br /> due to the reheater coils being out of service.

Repairs were completed to IMO-212 and the East CTS Pump was declared operable.

The Turbine Driven Auxiliary Feed Pump was declared in-operable at 0600 when it failed to meet the discharge pressure requirements at a flow of 700 GPM.

Retesting of the pump using test gauges determined the pump was satis-factory and it was declared operable at 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br />.

10/08/78 Radiation Monitors R-11 and R-12 were inoperable from 0300 to 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> because of failure of the paper; drive.

10/10/78 The North half of "B" Condenser was removed from service between 1054 and 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br /> to inspect for tube leaks.

3 tubes were plugged.

While this half of: the'ondenser was removed from service power was reduced to 855 megawatts to prevent exceeding the circulating water DT limits.

Docke Unit Name:

Date:

Completed By:

Telephone:

Page:

50-316 D.

C.

Cook Unit 82 November 14, 1978 R.

S. Keith (616) 465-5901 (2) 10/12/78--

(cont)

Radiation Monitor R-11 was declared inoperable at 2356 hours0.0273 days <br />0.654 hours <br />0.0039 weeks <br />8.96458e-4 months <br /> because of failure of the filter paper to remain in motion.

Radiation Monitor R-ll was declared operable at 0840.

10/17/78 The revision for the relocation, of the discharge check valve for the North Heater Drain Pump was completed and the pump was placed in service at 1235 hours0.0143 days <br />0.343 hours <br />0.00204 weeks <br />4.699175e-4 months <br />.

The South Heater Drain Pump was removed from service at 1242 hours0.0144 days <br />0.345 hours <br />0.00205 weeks <br />4.72581e-4 months <br /> to revise the discharge piping and relocate the check valve.

10/18/78 Radiation Monitor R-25 was out of service from 1023 to 1730 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.58265e-4 months <br /> for calibration.

10/19/78 The South Heater Drain Pump was pl.aced in service at 2150 hours0.0249 days <br />0.597 hours <br />0.00355 weeks <br />8.18075e-4 months <br /> and the Middle Heater Drain Pump was removed from service to revise the discharge piping and relocate the check valve.

10/24/78--

"AB" Emergency Diesel Generator engine failed to start twice.

The unit started on the 3rd attempt and it started successfully six additional times.

The frequency for starting these engines has been changed to once a week.

At 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> the solid state protection system Train "A" failed to 'test properly.

The unit was started down in power at 1645 hours0.019 days <br />0.457 hours <br />0.00272 weeks <br />6.259225e-4 months <br /> and the Reactor trip breakers were manually opened at 1734 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.59787e-4 months <br />.

The problem was identified to be a bad tester card.

The card was

replaced, the system tested and declared operable at 1930 hours0.0223 days <br />0.536 hours <br />0.00319 weeks <br />7.34365e-4 months <br />.

10/25/78 The Reactor was critical at 0430 hours0.00498 days <br />0.119 hours <br />7.109788e-4 weeks <br />1.63615e-4 months <br /> and the Generator was paralleled with the system at 0826 hours0.00956 days <br />0.229 hours <br />0.00137 weeks <br />3.14293e-4 months <br />.

Nhile the unit was out of service, Pressurizer Level Channel 1 alarmed with a level of 29Ã and a setpoint of 17Ã.

Repairs were made and it was declared operable at 1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />.

10/31/78 The Unit is operating at 90K power.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE MAJOR SAFETY-RELATED MAINTENANCE 50 - 316 D. C.

Cook - Unit No.

2 1-14-78 B. A. Svensson 616 465-5901

OCTOBER, 1978 CSI-1 East containment spray eductor inlet valve, IM0-212, stem broke while attempting to open.

Disassembled valve, fabricated new stem, reassembled and adjusted.

2AB diesel failed to start on two consecutive attempts.

Engine started on third attempt.

Found that fuel was not getting to the injector pumps.

Changed west duplex fuel filter and retested engine.

The rod position indication system for shutdown bank B rod C-9, would not respond when the rod was exercised.

The pins on the back of the panel indicator were cleaned, The indicator was reinstalled and tested.

CRI-2 CSI-3 P

CRI-4 C&1-5 The main turbine stop valve limit switches were not operating properly.

Solid state protection system train B input from stop valve D limit switch was found completely off the mount.

A spare limit switch was installed due to damage to the mounting holes of the limit switch.

The proximity type limit switch, supplying the signal to train A solid state protection system from stop valve D, was found to be loose.

A bolt was missing from the proximity switch mounting bracket.

Stop valve C was found to have the closed indication switch with one bolt sheared off and one bolt missing.

The main turbine stop valve C indication failed.

The closed limit switch on stop valve required replacement.

The limit switch linkage arm on the open limit switch also required replacement.

A ground condition was indicated on SIS monitor lights circuit 2.

The ground was located on IMO-910 indication status light No. 46.

A wire was shorting against the case.

The ground condition was cleared and the ground detector was reconnected.

During the start of the diesel driven fire pump on October 19, 1978, an approximate three second delay occurred between the run switch closure and the cranking of the engine.

Also the starter motor disengaged twice before the engine started.

The starting batteries were checked and a defective cell was found on "B" set of batteries.

Maintenance Department has placed an order for a replacement battery.

The control circuit dis-engages the starter motor for a ten second period following the starter motors operation for. a period of ten seconds.

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE PAGE MAJOR SAFETY-RELATED MAINTENANCE 50 - 316 D. C.

Cook - Unit No.

2 78 B. A. Svensson 616 465-5901

OCTOBER, 1978 During surveillance. test 2 THP 4030 STP.-.145, position 17 of switch "A",

position 22 of switch "B", and positions 16 to 23 of switch "D" failed to test as required.

Universal logic board A403 and a tester printed circuit board.required replacement.

Train A solid state protection system was returned to service.

The limit switches on the turbine main stop valves A and C would not operate properly.

The solid state protection system train B limit switch on stop valve A required lubrication to correct the sticking problem.

Solid state protection system train B limit switch on stop valve C re-quired replacement.

Also on stop valve C, the ssps train A limit switch'equired lubrication to correct the sticking problem.

Main turbine control valve D test circuit indicated a ground condition as the valve was tested.

A bare wire was located on the test solenoid valve caused by the solenoid coil vibrating.

The bore wire was repaired and a

washer added to the solenoid to prevent further coil movement.

Radiation monitoring system channel R-12 would produce a high level alarm and clear the alarm without the drawer assembly reset switch placed to the reset position.

The bistable circuit board P-3 was. replaced with a spare.

Surveillance test was performed to verify channel operability and setpoints of the bistable.

Pressurizer level protection set I low level safety injection bistable LB-459 A/B tripped at 27K level.

The required setpoint of the bistable is 175.

The LB-459 A/B duplex bistable required replacement with a spare module.

The spare bistable was calibrated and placed in service.

The axial power distribution monitoring system would continuously activate scans below 90% power.

The power level bistable indication lights in-dicated spurious operation of the bistable.

A functional test was per-formed on the system.

The setpoints for the power level actuation bistable was found to be 0.05 vdc low.

The bistables were calibrated.