ML17317A877

Monthly Operating Rept for Dec 1978

ML17317A877
Person / Time
Site:	Cook
Issue date:	01/03/1979
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317A876	List: ML17317A875 ML17317A877
References
NUDOCS 7901170271
Download: ML17317A877 (11)

Text

AVERAGE DAILYUNIT POWER LEVEL DOCK"7 NO.

UNIT DATE COMPLETED IIY V.T. Gullett TrLEPHONE 616-465-5901 December 1978 DAY AVERAGE DAILYPOWER LEVEL (MWe-Net }

I 948 DAY AVERAGE DAILYPOWER I.EVEL (MWe-Net )

1092 10 l3 I6 1070 944 1078 1078 1070 1070 10 1064 1090 1088 1088 1082 1087 1091 106 18 10 15 26 ZS

>9 30 31 1088 1077 1083 1090 1088 1071 1092 1094 1085 1075 937 969 1068 1088 INSTRUCTIONS On.his forrrat. list;he ave..a8e daily unit power ieve! in IIEVe-Yet for eath aay in th r porttnz tnonth. Compute tv tne near st whole tne8awatt.

(or 7)

OPERATING DATAREPORT DOCKET NO.

DATE 1 4

COgipLETED 8Y N. T. Giliett TELEPHONE 6~i~01 OPERATING STATUS Yfotes

l. Umt Name!

Donald C.

Cook 2

~

Re oaing Peaod.

December 1978

3. Licensed Thermal Pov/er P1Nt):

4. Namephte Rating (Gross MWe):

5. Design Electric Rating (Net MWe):

6. ~faximum Dependable Capacity (Gross MWe):

7. Maximum D endable Ca acit 'et MNe:

1 133 1 100 1,118 1,082

)

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

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

10. Reasons For Restrictions, IfAny:

Tins Month Yr:to.Date Cumulative 8,760 744 5 230.7 0

4,727.6 0

13 105 107 3 985 530 3.813 999 77.2 77.2 64.3 6.9

11. Hours In Reporting Period

12. Number Of Hours Reactor Was Critical 744 13; Reactor Reserve Shutdown Hours

14. Hours Genemtor On-Line 744

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 2 476 056

17. Gross Electrica Energy Generated (MNH)

18. i let Electrical Energy Generated (MWH)

19. Unit Service Factor

20. Uric AvailabilityFactor

21. Un!t Capacity Factor (Using MDC Net) '

22. Unit Capacity Factor (Using DER; let) 96.8

23. Unit Forced Outage Rate 2'. Shutdowns Scheduled Over Next 6 i~ionths (Type. Date. and Duration of Each):

8,760 5 230.7 0

4, 727. 6 13 105 107 3,985 530 3,813,999 77.2 77.2 65.3 6.9 25.

!f Shut Down At End Of Report Period. Estimated Date of Startup:

~

5. Units ln Test Status lPrior to Commercial Operation):

lNlTIAL CRITlCALITY lNlTIALELECTRICITY CO.'lMERCIAL OPERA TIOii Forecast 3/1/78 3/15/78

~6/1 78 Achieved 3/10/78 3/22/78 7/1/78

UNITSIIUTI)01VNS ANI)POIVER REI)UCTIONS l)OCKET NO.

,,~2 REPORT hlONlllDecember 1978 No.

l)arc El CL I-rv Q

u~ c

~ C/l CL Linc>>sec I!vent Report 4 tlc~

()

El O

CJ

(.a>>sc &,( ofllcove Aclii>>> lo Prcvc>>t Rccnfrco<<c 44 781228 S

0 N/A zz'ZZZZZZ Reactor power reduced to 70K to per-form N.I.S. Incore/Excore cross cal-ibration.

Power returned to 100Ã 781229.

I': I >>reed S:

Scl>eel>>legal I')/77)

Reasy>>r:

A-I'>>l>>ipr>> nr Failr rc(Explain)

I).hlai>>le>>ance or Tesi

('-Ref>> el hig I) Rcgolaloly Rcsrrr<<non I:-Opcraror Traioiog & Li<<<<>>s<< I xamioarion I"Ailminislrarivc (i OI>cratimwl Iaror ll:.xplai>>)

I I Oil>er (lixplain) 3 hlcll>>>d:

I.hlaooal 2 hla>>oal Serai>>.

3 Anil>>>>alic Scram.

~I Orl>cr (Explain)

I.xl>ibil G - Insiro<<rions for Preparario>> ol l)ara Entry Slrecls for Lice>>sec Eve>>I lleporl (I.I:R) File INURI:(I.

OI C) I )

I.xliibilI Saln<>>>lcc

UNITSHUTDOWNS AND POWER REDU NS LNSTRUCTIONS This report should describe all plant shutdov:ns during the report period.

In addition. it should be the source oicxplm-ation oi significant dips in average oower ievels.

Each signi.

iicant reduction in powe.

!eve! (gr ater thm 20% r duction in average daiiy power level ior 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 dov:n completeiyl.

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 Correcuve Ac:ion to Prevent Recurrence column should be used to provide any needed explanation to iully describe the circumstances of the outage or power reduction.

NUMBER.

This column shouid indicate the sequenti J~ num-ber assigned to each shutdov:n or significant reduction in power ior that calendar year.

When a snutdown or signiriicant power reduction begins in one report period and <<nds in another.

an entry should be made for both report periods to be sure Jl shutdowns or signittcant power reductions are reported.

UntQ 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 oi each shutdown or significant power reducuon.

Report as year. month. and day.

Auaust 14. 1977 would be reported as 770814.

When a shutdown or significant power reduc"on begins in one report period and ends in another, an eniry 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." respec:ivelv, ior each shutdown or significant power reduction.

Forcca 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 iorced shutdown is one that would not have been completed in the absence oi the conaition ior which corrective action was taken.

DURATION.

Sc!f~xpianatofy.

When a shutdown extends beyond the end ot a report period, count only the time to the end oi the report period and pick up the ensuing down time in the foi!owing f port periods.

Rcport duration of outages rounded to the nearest tenth oian hour to facilitate summation.

The sum oi the total outage hours plus the hours the genera-tor was on line shouia equal the gross hours in the reporting period.

REASON, Categorize by ic.'ter designation in accordance with the table appearing on the report t'orm. Ifcategory H fnust he used. supply brief comments.

METHOD OF SHUTTING DOWN THE REACTOR OR REDUCING POWER.

Categorize by numher designation INoie that this diiiers i'rofn the Edison Eie;tric institute

{EEI) definitions oi -Forced Partial Outage" and

-Sche-duled Partial Outag

~." Fof these tenn~. f'El uses

~ cilange oi

.0 ~IW as thc ofcak point.

Filf larger power reactors. ~0 MW is 1>>o small u 'hangc t<<warrant cxpianatii>>i.

in accordance with the table appearing on the report form.

Ifcategory -'ust be used. supply brief comments.

LICENSEE EVENT REPORT =.

Reierencc the appBcable reportable occurrence pertaining to the outage or power reduction.

Enter the first iour parts (event year. sequenual report numbe:, occurrenc code and report type) of the five part designation as described in Item 17 oi Instructions for Preparation of Data Entry Sheets ior Licensee Event Reoort (LER) File (NUREG4161).

This information inay not be immediately evident for all such shutdowns. oi course, since further investigation may be reauired to ascertain whether or not a reportable occurrence was involved.) lithe 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 powc.

reduction originated should be noted by the two digit code of Exhibit G - Instructions for Preparation oi Data Entry Sheets for Lic nsee Event Rcport (LER) File (NUREG4161).

Systefns 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.

'OMPONENT 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 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 ttt any existing code snouid be de.

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

component designation is not applicable.

CAUSE & CORRECTIVE ACTION TO PREVENT RECUR-RENCE.

Use the column in a narrative fashion to ampiiiy 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 immediate and contemplated long term corrective action taken. if appropri-ate.

This oiumn should also be used ior a description oi the major safety related corrective maintenance performed during the outage or power reduction including an identification oi the critical path ac:ivity and a report of any single release oi radioactivity of single radiation exposure specifically associ.

ated with the outage which accounts ior more than 10 percent oi the allowaole annual values.

For long textual reports continue narrative on separat paper and fcicrcncc flic shutdown of powc, fcauciioil iol ting ila ffa tive.

(L) I

Docket o.:

Unit Name:

Completed By:

Telephone:

Date:

50-316 D.

C.

Cook Unit 42 R.

S.

Lease (616) 465-5901 January 9,

1979 OPERATING EXPERIENCE DECEMBER, 1978 Hi hli hts The Unit has operated at power the entire reporting period.

Most of this time has been at'00'X power.

There have been short term power reductions to as low as 70Ã.

Summar 12/Ol/78 The Unit entered this reporting period operating at 905 power and 970 megawatts electrical.

Loading is limited due to the "A" string of high pressure heaters being out of service to repair a manhead leak on the b5 heater.

The "A" string of high pressure heaters was returned to service at 2115 and the Unit was loaded to 1005 power, 1170 megawatts electrical, by 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br />.

12/02/78 Unit loading was reduced to 90Ã power, 970 megawatts electrical, between 2200 and 2300 hours0.0266 days <br />0.639 hours <br />0.0038 weeks <br />8.7515e-4 months <br /> to remove the "B" string of high pressure heaters from service to repair a leak on the manhead of 5B heater.

These heaters were returned to service by 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> and the Unit was loaded to 100K power, 1170 megawatts electrical, by 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br />.

The Control Room Cable Vault Halon Fire Protection System was inadvertantly discharged at 1202 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.57361e-4 months <br />.

This was caused by the operator pushing the actuation button on the control panel rather than the reset button.

These two buttons look alike and are mounted close together on the same panel.

The Halon bottles were replaced and the system returned to normal at 2210 hours0.0256 days <br />0.614 hours <br />0.00365 weeks <br />8.40905e-4 months <br /> December 4, 1978.

12/04/78 At 1810 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.88705e-4 months <br />, both Main Feed Pump Turbines were placed on reheat steam operation.

This is the first that both of these turbines operated on reheat steam at the same time.

The reheat steam pressure is still marginal.

Radiation Monitors R-ll and R-12 were inoperable for a

15 hour1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> period while the pump supplying both of these monitors was repaired.

Docket~.:

Unit A%Tie:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit f2 R.

S.

Lease (616) 465-5901 January 9,

1979 (2) 12/06/78--

12/07/78--

Unit power was reduced to 905, 970 megawatts electrical, between 2144 and 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br /> because of fluctuating feedwater heater levels.

The heater drain system was stabilized and the Unit reloaded to 1005 power between 2225 and 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br />, 1170 megawatts electrical.

Electrical'eneration slipped off to 1100 megawatts electrical due to degraded Condenser vacuum.

"A" Condenser vacuum breaker valve was found to be leaking through.

This is a water sealed valve and an additional supply was rigged to the valve and the vacuum returned to normal.

Emergency safeguards exhaust fan HV-AES-02 was out of service for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to repair the rolla-matic filters.

Radiation Monitors R-25 and R-26 were out of service for a period of 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> to repair the pump that supplies both monitors.

12/08/78--

12/09/78 Power was reduced to 905, 970 megawatts electrical, at 2240 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.5232e-4 months <br /> for testing of Turbine valves.

Power was returned to 100K power by 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> December 9, 1978.

Power was reduced to 88%,

950 megawatts electrical, at 1153 hours0.0133 days <br />0.32 hours <br />0.00191 weeks <br />4.387165e-4 months <br /> due to decreasing condenser vacuum.

The additional water supply is no longer sufficient to the "A" Condenser vacuum bi eaker.

This vacuum breaker was blanked off and power was returned to 99K.

On the previous transient, emergency boration had been used to get back within the axial flux target band.

When power was almost 1007.,

a small boration was required,

however, the emergency boration valve had been left open and power was again reduced to 85/.

Power was returned to 1005, 1170 megawatts electr ical, at 1410 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.36505e-4 months <br />.

12/15/78 Power was reduced to 90K at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> for testing of Turbine valves and was returned to 1004, 1170 megawatts electrical, by 0215 hours0.00249 days <br />0.0597 hours <br />3.554894e-4 weeks <br />8.18075e-5 months <br /> December 16, 1978.

Turbine Driven Auxiliary Feed Pump was out of service for an 8.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period to repair a steam leak.

12/17/78-- At 2127 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.093235e-4 months <br />, the air pump for Radiation Nonitors R-ll and R-12 tripped due to high air flow when the filter paper ran out.

The paper was renewed and the pump and monitor s were returned to service at 2142 hours0.0248 days <br />0.595 hours <br />0.00354 weeks <br />8.15031e-4 months <br />.

S

Dock~o.:

Unit~me:

Completed By:

Telephone:

Date:

Page:

50-316 D.

C.

Cook Unit ¹2 R.

S.

Lease (616) 465-5901 January 9,

1979 (3) 12/19/78 The North half of "A" Condenser was out of service for a period of 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> for plugging of 3 leaking tubes.

12/20/78 The South half of "B" Condenser was out of service for a 9.7 hour8.101852e-5 days <br />0.00194 hours <br />1.157407e-5 weeks <br />2.6635e-6 months <br /> period.

No leaking tubes were identified.

12/22/78--

12/23/78--

Unit loading was reduced to 905 starting at 2313 hours0.0268 days <br />0.643 hours <br />0.00382 weeks <br />8.800965e-4 months <br /> for testing of Turbine Valves and returned to 100K

power, 1170 megawatts e'lectrical, by 0300 hours0.00347 days <br />0.0833 hours <br />4.960317e-4 weeks <br />1.1415e-4 months <br /> December 23, 1978.

The Fire Protection Spray System operated on the charcoal filters in the Control Room pressurization fan system.

Both pressurization fans were found to be inoperable at 1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />.

The trouble was found to be water had seeped into the fire spray actuation control box.

This control box was dried out and one fan was operable at 1541 hours0.0178 days <br />0.428 hours <br />0.00255 weeks <br />5.863505e-4 months <br /> and the other fan operable at 1547 hours0.0179 days <br />0.43 hours <br />0.00256 weeks <br />5.886335e-4 months <br />.

12/25/78 The North half of "A" Condenser was out of service for a 10.25 hour2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period for plugging of 3 leaking tubes.

12/27/78 The South half of "B" Condenser was out of service for a period of 13.25 hours2.893519e-4 days <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br />.

No leaking tubes were iden-tified.

12/28/78-- Unit power was reduced to 70%,

770 megawatts electri-

cal, between 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> and 1625 hours0.0188 days <br />0.451 hours <br />0.00269 weeks <br />6.183125e-4 months <br /> for incore/

excore nuclear instrumentation cross calibration.

The Unit was reloaded to 1005 power, 1170 megawatts elec-trical, between 0412 hours0.00477 days <br />0.114 hours <br />6.812169e-4 weeks <br />1.56766e-4 months <br /> and 0950 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.61475e-4 months <br />, December 29, 1978.

12/29/78--

12/30/78 Unit loading was reduced to 90/ power starting at 2313 hours0.0268 days <br />0.643 hours <br />0.00382 weeks <br />8.800965e-4 months <br /> for testing of Turbine valves and was returned to 100K power, 1170 megawatts electrical, by 0212 hours0.00245 days <br />0.0589 hours <br />3.505291e-4 weeks <br />8.0666e-5 months <br /> December 30, 1978.

¹21 Circulating Water Pump started making noises.

This pump was removed from service and adjustments were made.

Two re-runs of the pump were made and it was still noisy.

This pump was left out of service at 2252 hours0.0261 days <br />0.626 hours <br />0.00372 weeks <br />8.56886e-4 months <br />.

With only 3 Circulating Mater Pumps operating rather than the normal 4, we were operating near the maximum allowed temperature rise of the circulating water through the condenser.

vw

DOCKET NO.

50 - 316 UNIT NAME D.

C.

Cook - Unit No.

2 DATE 1-10-79 COMPLETED BY B. A. Svensson TELEPHONE 6 6 465-5 0

MAJOR SAFETY-RELATED MAINTENANCE DECEMBER 1978 M-1 M-2 C&I-1 Motor operated auxiliary feed isolation valve to 83 S/G, FMO-232 would not operate properly.

Investigation located a broken internal jumper wire.

Valve was repaired and retested.

No.

2 S/G stop valve dump valve, MRV-221 was leaking by.

Disassembled valve, replaced plug, stem, seat and all gaskets.

Reassembled and had valve functionally tested.

PPP-301, lower containment pressure protection channel ITT, indication on recorder 2MR-035 failed low.

The instrument protection set panel indication was verified as correct.

The recorder was calibrated and returned to service.

C&I-2 aT/Auctioneered 4T Lo Alarms Annunciator Drops 36, 37, 38 and 39, were inoperable.

The wires on DB12-1 and 12-2 rack 24 were found loose re-sulting in an incorrect voltage at the input of TY-411J (current re-peater).

The wire terminators were tightened and the loop returned to service.

C&I-3

'&I-4 C5I-5 Radiation Monitoring System, Channel R-32, failed to respond to the check source.

The detector tube required replacement, Surveillance test was performed for verification of correct operation.

The reactor protection safeguards train in test alarm was received and the alarm light in the safeguards Train B cabinet was illuminated.

A loose terminal connection on relay K801 allowed the wire lug on the terminal to short to an adjacent contact and energizing relay K815.

Relay K815 produced the alarm.

The lug was repositioned and tightened.

The control room pressurization fan would not start as required.

The remote start-stop pushbutton was found filled with water.

The water was removed and the contacts of the switches cleaned.

The correct starting of the fan was verified.

~$

R;I