ML17317B461

Monthly Operating Rept for Jul 1979

ML17317B461
Person / Time
Site:	Cook
Issue date:	08/07/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317B460	List: ML17317B459 ML17317B461
References
NUDOCS 7908170343
Download: ML17317B461 (11)

Text

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AVERAGE DAI' UNliPOb:R '-VEL DAT="

COMPLETED BY i =LEPHOi'lE 8-7-79 616-465-5901 MOD@~

DAY AYERAGE DAlLYPO4'ER L=VEL

(,'vl'We-: le~)

0 0

239 1,033 1,055 DAY A'i'ERAGE DAlLYPO4'ER LD'EL (MWe.'(et) 1,053 1,036 1 '043 638 10 15 1,054 1,058 1, 058 1,053 1,050 1,044 1,042 1,051 1,045 1,040 1,024

'i5 o5 ZS 19 30 997 1,033 1,029 1,033 1,036 1,036 1,015 1,039 1,035 1,019 (NSTRUC i iOi45

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OPERATLNG DATAREPORT OPERATING STATUS Donald C.

Cook 2

I. Unit Namet

2. Reporting Periodt

3. Licensed Thermal Power P IWt):

4. Nameplate Racing (Gross MWe):

S. Design Elecni& R".ing (Net iaaf We):

6. >faximum Dependable Capacity (Gross bfWe):

7. Nfaximum Dependable Capacity (iiiec MWe)t 3 391 1,133 1,100 1,118 1,082 Notes DOCKET NO DAt COiIPL~ED SY W.T. Gilleet TELEPHONE Si~~M901 S. IfChanges Occur in Capacity Ratings (Items Number S Through 7) Since Last Report. Give Reasons:

9. Power Level To Whi"<<'t Restzictnf, IfAny (Net ilfWe):

10. Reasons For Restrictions, IfAny:

11. Hours In Reporting Period IZ. Number Of Hours Reactor Was C.":nM

13. Re ctor Reserve Shutdown Houa

14. Hours Generator On-Lbt IS. Unit R~rve Snutdown Hots

16. Gross Thermal Energy Generat d (MWH)

17. Gross Elemc3 Ener,y Generated (i~IWH)

18. Ne! Electrical Energy Generat d PDVH)

19. Unit Service Factor ZO. Urit Availability Factor ZI. Unit C"pacity."actor (Using ~!DC Net) 2". Unit Capacity Factor (Using DER Net)

~~. Unit Forced Outaoe Rate

24. Shutdowns Scheduled Ove. Next 6 Months This Month 744 690. 9 0

678.3 0

2 258 164 720,360 694 686 91.2 84.9 8.4 Yr.-to-Date 5,087 3 951.3 0

3 882.0 0

12 816,511 4,157,290 4,013,065

76. 3 76.3 72.9 71.7 23.6 (Type. Date. and Du:ation of Each):

Cumula! ive 13,847 9 182.0 0

8 609.6 0

25,921,618 8,142,820 7,827,064 76.7 76.7 69.4 68.3 1

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"5. IfShut Down At End Oi Report Period. Estimated Date of Startuo:

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"5. Units In Test Scatus (P.:or to Commercial Operation):

r orec st Achieved INITIAL CRITICALITY INITIALELECT? ICITY CO'I.'iIE? CIALOPERATION

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UNITSllUTDOlVNSAND PO)UER REDUCT(ONS RFPORT MON.fllJULY, 1979 2

DOCKET NO. lrIT79 D

Ni).

Dale PI Vl J

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Ln:cnscc Event Rcport 4 c~

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Cause &Corrcclivc Acl)on lo Pfcvcnl Rccurrcnec 59 790519 F

62.0 A

1 79-019/01T-0 FW PIP EXX Outage continued from previous month.

Unit returned to service on 790703 at 1358 hours0.0157 days <br />0.377 hours <br />0.00225 weeks <br />5.16719e-4 months <br />.

Total outage time 1076.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

60 790721 S

3.7 8

2 N.A.

zz zzzzzz Unit tripped manually from 1005 power using the generator trip button.

Purpose of trip was to collect data on feedwater elbow/steam generator nozzle test instrumentation during trip and recovery transient.

Data was also collected for the re-quired generator 100/ load trip.

Unit returned to service the same day and reached 1005 reactor power on 790722.

f: Forccll S: Scheduled

(')/77)

Reason:

A.l:Ilu)pn)cnl Fa)lul'c (Explan))

f)-h(aintcnance oi Test C-Rcfucli>>g D Regulatory Reslriclion f -Operator Training & License l:xan))nation F-Adn)inist rat ivc G.Operational Lrror (l'.xplain) l I.Oll)cr (Explain) 3 hlelhod:

I.hla no el

) Manual Sera)n.

3-Aulon)alic Scran).

0-Otl)er (Explanl)

Exl))b)t G - instruct)ons for preparation of Data Lntry Sl)eels I'or L)ccnsec Event Rcport (l.LR) File (NUREG-0(6l )

5

'Lxl)ibil I - Sa)ne Source

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 daBy 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 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'olumn 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 Jl shutdowns or significant power reductions are reported.

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

DATE.

This column should indicate the date of the start of each shutdown or signiricant power reduc:ion.

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 action was taken.

DURATION.

Seif~xplanatory.

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

Report duration of outages rounded to the nearest tenth of an hour to faciTitate 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.

Cateanrize by letter designation in accordance with the table appearing on the report form. Ifcategory H must be used. suppiy brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by number designation iN>nie that this difters irnm the Edison Eie tric Institute

{EEI) definitions of -Forced Partial Outage" and

-Sche-duled Partial Outage."

F<>r these tern>>. EEI uses a change of

.0!>IW as the break point.

For larger pov er reactors.30 MW is ts>i> small a change to warrant cxplanatin>i.

in accordance with the table appearing on the report form.

Ifcategory 4 must be used, supply brief comments.

LICENSEE EVENT'EPORT =.

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

Enter the tirst 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 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 be used for those events where a system is not applicable.

COMPONEiNT CODE.

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

using the following critieria:

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

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

e.g..

wrong valve operated through error: list vaive 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 8: 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-rehted corrective maintenance performed during the outage or power reduction including an identification of the critical path activity and a report of any single reiease of radioactivity or single radiation exposure specitically associ

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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 an>1 ret'erence tile shutdown or power reduction inr th>>

>la ffa tIve.

(')l77

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 82 R.

S.

Lease (616) 465-5901 August 8, 1979 1 of 2 MONTHLY OPERATING EXPERIENCES -- JULY, 1979 Hi hli hts At the start of the reporting period this Unit was in Mode 3 returning from an outage for replacement of feedwater elbows.

Total electrical generation for the month was 720,360 Mwh.

Summar 07/02/79 -- The Condensate System contamination that was reported in last month's report was cleaned up and refilling of the system was initiated at 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />.

Reactor Coolant System operating temperature and pressure was obtained.

The Reactor was critical at 1849 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.035445e-4 months <br />.

At 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> a Safety Valve on 83 Steam Generator opened.

This valve did not reset until pressure was reduced by 200 psi.

Control rods were driven in to make the Reactor sub-critical with Reactor Coolant System temperature less than 541 Reactor over-power trips were reset to 85K and the safety valve that had lifted was gagged to allow it to cool.

The Reactor was returned to critical, at 2314 hours0.0268 days <br />0.643 hours <br />0.00383 weeks <br />8.80477e-4 months <br />.

07/03/79 -- The Main Turbine was rolled at 0331 hours0.00383 days <br />0.0919 hours <br />5.472884e-4 weeks <br />1.259455e-4 months <br />.

The Main Turbine was brought up to, speed and just prior to the moment of parallel to the system, the Unit and Reactor tripped at 0453 hours0.00524 days <br />0.126 hours <br />7.490079e-4 weeks <br />1.723665e-4 months <br />.

Cause of the trip was low vacuum in the "A" Condenser.

The Reactor was returned to critical at 1022 hours0.0118 days <br />0.284 hours <br />0.00169 weeks <br />3.88871e-4 months <br />.

The Turbine was rolled at 1242 'hours and the Generator paralleled to the system at 1358 hours0.0157 days <br />0.377 hours <br />0.00225 weeks <br />5.16719e-4 months <br />.

The Unit was loaded to 80% power by 2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />.

The gag that had been previously installed on the safety valve was removed and the overpower trips reset to normal.

P Lb

Docket No.:

Unit Name:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit 82 R.

S.

Lease (616) 465-5901 August 8, 1979 2of2 07/04/79

. The Unit was loaded to 905 power at 0105 hours0.00122 days <br />0.0292 hours <br />1.736111e-4 weeks <br />3.99525e-5 months <br /> and 100K by 0420 hours0.00486 days <br />0.117 hours <br />6.944444e-4 weeks <br />1.5981e-4 months <br />.

The new feedwater elbows for Steam Generators 1 and 3

had been equipped with multiple instrumentation.

These instruments consisted of thermocouples,'ccelerometers, strain gauges and flow measurements, being a total of greater than 50 on each elbow.

These special instruments were monitored all during the startup and loading process.

07/15/79 -- At 2145 hours0.0248 days <br />0.596 hours <br />0.00355 weeks <br />8.161725e-4 months <br /> the normal heater drain valve between heaters 5B and 4B wasiremoved 'from service to repair a

flange leak:.,

This required removal of the heater drain pump from service on this set of heaters.

Electrical load loss amounted to 30 megawatts.

Repairs were made and the Unit ret'urned to normal generation at 2212 hours0.0256 days <br />0.614 hours <br />0.00366 weeks <br />8.41666e-4 months <br /> 7/16,!79.

07/18/79 07/19/79 The "CD" Emergency Diesel Generator was inoperable for a 7.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for repair to a check valve in the air-line to the Turbo-Supercharger.

Unit power was. reduced;to 97K between the hours of 0010 and 0540 for a Moderator Temperature Coefficient Test.

07/21/79 07/22/79 07/28/79 07/31/79 The Unit was intentionally tripped from 100%%d power at 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br />.

This was part of the test program to determine why the cracks had developed in the feedwater lines.

The method of trip was Generator trip,which also satisfied one of our required preoperational tests.

The Reactor was returned to criticality at 1444 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.49442e-4 months <br />..

The Turbine was rolled at 1533 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.833065e-4 months <br /> and the Generator paralleled to the system at 1550 hours0.0179 days <br />0.431 hours <br />0.00256 weeks <br />5.89775e-4 months <br />.

The Unit was loaded to 100Ã power by 0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />.

-- Unit power was reduced from 95/ between the hours of 2150 and 2320 for testing of Turbine valves.

Power was reduced to 905 between the hours of 0155 and 0521 hours0.00603 days <br />0.145 hours <br />8.614418e-4 weeks <br />1.982405e-4 months <br /> for repair of a seal oil leak on the Turbine end of the Main Generator

I IP A

DOCKET NO.

UNIT NAME DATE COMPLETED BY TELEPHONE 50 - 316 D.

C.

Cook - Unit No.

2 8-13-79 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE JULY, 1979 HARV-251, seal injection flow control valve would not operate.

The valve stem was replaced.

Retest was satisfactory.

Check valve, DG-128C, on diesel generator air receiver 2-CD2 was leaking by.

Disassembled

valve, lapped seat and reassembled.

The high and low alarm for accumulator No.

1 was received simultaneously from IPA-110 and IPA-111.

The bistables of the instrument loops were calibrated.

The as-found calibration of 2PB-960 A/B was out of speci-fications.

The urgent failure alarm on control rod drive system was received.

The alarm was the result of the firing control circuit card.

The printed circuit board was replaced,and the alarm reset.

Operation of the system was functionally tested.

MPP-220, steam generator No.

2 pressure protection set, indication was incorrect.

The calibration of the transmitter was verified to be correct.

The panel indicator was removed and zeroed.

The panel indication returned to the correct value.

Radiation monitoring system channel R-25 paper drive would only operate in -the fast paper mode.

The slow speed drive motor was removed and re-placed with a spare motor.

Correct operation of the filter paper drive system was verified.

Unit 2 axial power distribution monitoring system would only produce a

1-3 detector scan.

The input circuit card-malfunction produced the error in operation.

The input circuit card was replaced with a spare and a functional test performed.

Radiation monitoring channel R-32; Unit vent radio iodine monitor, high alarm was received periodically without apparent cause.

The dual log-rithmic counting circuit card in the counting ratemeter was replaced and cal,ibration was performed.

Panel rod position indication for rods C-7, N-7, N-9, C-ll, C-5 and N-ll deviated greater than 12-steps from the demand position.

The secondary coil voltages were measured and verified to be'orrect.

The signal con-ditioning modules were calibrated for the correct output signals.

DOCKET NO.

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

C.

Cook - Unit No.

2 8-13-79 B. A. Svensson 616 465-5901 bt JULY, 1979 II The rolamatic filters on 2-HV-AES-1 and 2-HV-AES-2 would not operate as required.

The automatic timer was found to be adjusted for advancing the filter once per 120-hour.

The timer was adjusted to provide seven advances per 120-hour period.

The.,v'rind direction indication at the 150 foot level had failed low.

The direction signal was switched to the secondary system.and indica-tion returned to normal.

Bad weather conditions have prevented climbing the weather tower to remove primary sensor for repair.