ML17317A665

Monthly Operating Rept for Sept 1978

ML17317A665
Person / Time
Site:	Cook
Issue date:	10/03/1978
From:	Gillett W INDIANA MICHIGAN POWER CO.
To:
Shared Package
ML17317A664	List: ML17317A663 ML17317A665
References
NUDOCS 7810200056
Download: ML17317A665 (9)

Text

i

~ ~

~

~bar V t~

Ab~AF AVERAGE DAILYUNITPOWER LEVEL DOCKET NO UNIT 10/3/78 COMPLETED BY N. T. Gillett TELEPHONE 616 465 590 1 September 1978 DAY AVERAGE DAILYPOWER LEVEL IMWe-Net) l 0

180 701

]7 l8 938 927 DAY AVERAGE DAILYPOWER LEVEL (MWe Net) 923 IO

)3 14 15 16

'83 825 895 921 916 868 917 915 886 822 934 921 20 21

'l5 27 28

'79 30 31 961 1,030 1 019 1,031 952 1, 017 883 1,020 1,017 1,017 969 INSTRUCTIONS On this format. )is: the averaee daiiv unit povver level;n i)iVe.iet for each day in the repurttne m mth. Compute to the nearest v-hole mega~vat t.

(rtr77 I' QQ+oe05 0

OPERATING DATAREPORT DOCKET P'O.

D6TE ~23/18 COMPLETED BY M~~3.1ett

. TELEPHONE ~616-465-801 OPERATNG STATUS Donald C. Cook 2

2. Reporting Period:

e e~

1978

3. Licensed Thermal Power Pf)Vt):

4.: nameplate Ra ting (Gross LbfIVe):

S. Design EiecuiM Rating (Net 6!fNe):

6. ~faximum Dependable Capacity (Gross MNe):

7. Maximum Dep ndable Capacity {NetkfWe):

3,391 1,133 1,100 1 082 Yotes S. IfChanges Occur in Capacity Ratings (Items Aumber 3 Throu~. 7) Since Las; R port. Give Reasons:

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

10. Reasons For Restrictions. IfAny

11. Hours ln Reporting Period

12. Number Of Hours Reactor %as Critical 13: Reactor Reserve Shutdown Hoax

14. Hours Gener tor On-Line

15. Unit Reserve Shutdown Houa

16. Gross Thermal Energy Generated

(!PI~VH)

I"J. Gross Electric I Energy Gen r ted (MNH)

18. Yet Electrical Energy Generated (Af'O'H)

19. Unit Service Factor

20. Unit AvailabilityFactor

21. Un!t Capaci'v Factor (Usino lLIDCYet) 2". Unit Capacity Factor (Using DER ib t)

M. Unit Forced Outage Rate

24. Shutdowns Scheduled Over LNext 6 Months This Month 7.2 0

682. 5 651,870 Yr..to.Date 6,S51 0

2 929.9 0

7 549 698 2 226 860 2

22 73.0 59.9

58. 9 12.3 94.8 80.3 79.0 5.2 IType. Date. and D"wtionof Each):

Cumulative 3 397.6 2 929.9 7 549 6 8 2 226 860 2122 4

73.0 73.0

.9 58.9 12.3

5. I&hut Dov'n At End Of Report Period. Estimated Date ot Startup:

-'6. Uni!: In Test Status Iprior to Commercial Operation):

INITIALCR!TICALITY liiITIALELECTRICITY CO: IilERCIALOPERATIOY Forecast 3/1/78 3~15~8 Achieved 3/10/78

~322~

UNITSIIUTI)01YNS ANI)POIUER REI)UCTIONS DOCKETNo.

REI'0RThioNfll September, 1978 No.

p

~

I-P

~tl f<

r 0 M Q m ~r>e U~ r

~ <I) p Liecnscc I!vent llcpofl rr C~

0 Vl

'G orill p 0 p

Q Cause h. Corrective Action to Prcvcnt Rceurrcnec 34 35 36 37 780827 780913 780926 780930 37.5 0

0 0

H 3

B 4

H 4

B 4

N/A N/A 78-071/03L-0 N/A ZZ ZZZZZZ ZZ Zzzzzz ZZ Zzzzzz ZZ ZZZZZZ Outage continued from previous month.

Unit returned to service 780902.

Total outage time 148.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br />.

Reactor power reduced to 70$ to per-form N.I.S. Incore/Excore cross cal-ibration.

Power returned to 97K 780914.

The ice condenser inlet doors were moved from their closed position when starting containment air recircula-tion fan for surveillance test.

Re-actor power was reduced to 20% to permit entry into the lower ice con-denser to close the doors.

Power returned to 1005 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> later.

Reactor power reduced to 60K to per-mit change out of pressure control-lers in the main steam supply to the main feed pump turbines.

Power re-turned to

'lOOA 13 hours1.50463e-4 days <br />0.00361 hours <br />2.149471e-5 weeks <br />4.9465e-6 months <br /> later.

I': FolecJ S: SeheJutcJ IIeas<ul:

A.l!<Iuipn>cnl Failure (Explain)

I).hIalnten;n>ec or Test C. Refueling I) Ret,ulato>y Rest>ietiun I!.Ot>er;>tor Trai>>i>>g & Uce>)sc llxan)lnatlon F AJnun>stra)>vc 0 Oi>e<ational I >r<>r (lixpialn)

II'Other (I:XplJhl)

McthoJ:

I.hla>>oal 2 h(anual Sera>n.

3.Anton>alic Seranl.

4-Other (L'xplain)

Exhii>lt G-Instructions for Preparation ol l)ata L>ntry Sheets for I.ieensec Invent Repor t (I.I!R) File (NIIRL'G-Ol6l )

L'<Ilibit I SJn)L Soul<.L

Docket No.:

50-316 Unit Name:

D.

C.

Cook Unit f2 Date:

October 12, 1978 Completed By:

R. S. Keith Telephone:

(616) 465-5901 OPERATING EXPERIENCE - SEPTEMBER 1978 Hi hli hts Unit 2 was on line 28 out of the 30 days of the month.

Sugar 9/1/78 9/2/78 9/3/78 9/5/78 The Unit entered this reporting period with the reactor.in Hode 3 and the main turbine generator was off the turning gear to affect repairs to the front standard.

At 1230 hours0.0142 days <br />0.342 hours <br />0.00203 weeks <br />4.68015e-4 months <br /> the CD emergency diesel generator was declared inoperable because of fuel oil leakage into the lube oil system.

CD emergency diesel generator lube oil had been changed and the engine was declared operable at 0541 hours0.00626 days <br />0.15 hours <br />8.945106e-4 weeks <br />2.058505e-4 months <br />.

'The reactor was critical at 0846 hours0.00979 days <br />0.235 hours <br />0.0014 weeks <br />3.21903e-4 months <br />.

The turbine generator was rolled at 1006 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.82783e-4 months <br /> and tripped at 1203 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.577415e-4 months <br /> due to high steam generator level while placing main feed water in service.

Hhen the steam generator level had reduced, the main feed water system was again placed in service and the main turbine generator returned to full speed.

110Ã and 112Ã overspeed trip on the main turbine generator were tested.

The turbine generator was paralleled with the system at 1329 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.056845e-4 months <br />.

The Unit was loaded to 58Ã by 2000 hours0.0231 days <br />0.556 hours <br />0.00331 weeks <br />7.61e-4 months <br /> and held at this power due to minimum system loading conditions of the holiday weekend.

The Unit was loaded to 80'A at 0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br /> and held at this power due to no heater drain pumps available.

The Unit was loaded to 90Ã power.

The 4KV cables between transformer 201-CD and the switch gear were showing signs of deteriation in the stress cone in each cable.

This had been caused by the cable shield being grounded at both ends.

Rod position indication for control rod C-9 was inoperable for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

The motor driven auxiliary feed pump was inoperable for 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

t Docket No.:

Unit Name:

Date:

Completed By:

Telephone:

Page:

50-316 D.

C.

Cook Unit f2 October 12, 1978 R. S. Keith (616) 465-5901 82 9/6/78 9/10/78 I

The Unit was loaded to 97Ã power.

Power was reduced to 855 to test turbine valves and to change lube oil in the inboard motor bearing of the South condensate booster pump and the outboard motor bearing on the North condensate booster pump.

Power was returned to 97K at 1443 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.490615e-4 months <br />.

9/11/78 The 201-AB transformer was out of service for cable inspection.

The AB emergency diesel generator was started for required surveillance test.

One of the starting air check valves leaked, allowirig cylinder exhaust gases to backfeed into the starting air line.

The engine was declared inoperable at 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />.

Repairs to the starting air check valve were completed and AB engine diesel generator was operable at 2310 hours0.0267 days <br />0.642 hours <br />0.00382 weeks <br />8.78955e-4 months <br />.

9/12/78 4 fuel oil leaks were identified on CD emergency diesel generator.

9/13/78 9/14/78 Power was reduced to 70~~ at 1805 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.868025e-4 months <br /> to perform Incore/Excore Instrumentation Cross Calibration.

Incore/Excore Instrumentation Cross Calibration was completed and the Unit returned to 97K power at 1150 hours0.0133 days <br />0.319 hours <br />0.0019 weeks <br />4.37575e-4 months <br />.

Fuel oil leaks on the CD Emergency Diesel Generator were repaired and the engine declared operable at 1638 hours0.019 days <br />0.455 hours <br />0.00271 weeks <br />6.23259e-4 months <br />.

9/17/78 Power was reduced to 85K to test turbine valves and then returned to 97K.

9/18/78 9/19/78 Rod position indication for control rod H-8 indicated a greater than 12 step deviation from the other rods of its group for.a

'2 hour2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> period.

The West RHR pump was inoperable for 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> and 10 minutes to affect repairs to an auxiliary switch.

Reactor Coolant System loop 1 Over-Power/Over-Temperature hT protection was inoperable at 1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br /> and the protection system was placed in trip.

9/20/78 Reactor power was increased to 100K at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br />.

9/21/78 Reactor Coolant System loop 1 Over-Power/Over Temperature hT protection was restored to operation at 0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />.

The turbine dr iven auxiliary feed pump was declared inoperable at 1647 hours0.0191 days <br />0.458 hours <br />0.00272 weeks <br />6.266835e-4 months <br /> because of an oil leak.

Docket No.:

Unit Name:

Date:

Completed By:

Telephone:

Page:

50-316 D.

C.

Cook Unit 0'2 October 12, 1978 R. S. Keith (616) 465-5901 83 9/22/78 Turbine driven auxiliary feed pump was operable at 0157 hours0.00182 days <br />0.0436 hours <br />2.595899e-4 weeks <br />5.97385e-5 months <br />.

Radiation monitor R-25 was inoperable from 0200 to 0315 hours0.00365 days <br />0.0875 hours <br />5.208333e-4 weeks <br />1.198575e-4 months <br /> because the filter paper drive did not operate.

Nuclear instrumentation N-44 was inoperable from 2000 to 2057 hours0.0238 days <br />0.571 hours <br />0.0034 weeks <br />7.826885e-4 months <br /> to repair a high voltage cable connection.

Instrumentation was placed in trip while the repairs were made.

9/24/78 Power was reduced to 85% power at 0105 to test turbine valves and power was returned to 1005 at 1343.

9/26/78--

9/30/78 At 1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br /> all but 2 of the lower ice condenser doors came open.

Testing of the Containment Equalizing fan was in progress.

Reactor power was reduced to 20% to permit entry into the ice condenser to close the doors.

All of the doors were closed at 1223 hours0.0142 days <br />0.34 hours <br />0.00202 weeks <br />4.653515e-4 months <br /> and the reactor returned to 100% power at 1832 hours0.0212 days <br />0.509 hours <br />0.00303 weeks <br />6.97076e-4 months <br />.

During the down power transient which was made with the control rods, the reactor was out of the target band from 1047 to 1119 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.257795e-4 months <br />.

Power was reduced to 605 starting at 2212 hours0.0256 days <br />0.614 hours <br />0.00366 weeks <br />8.41666e-4 months <br />.

Both main feed pumps were transferred to reheat steam one at a time to replace the transmitters from the main steam supply valves ARV-ll and ARV-12.

I IQ ~"j'

~

t DOCKET NO.

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

C.

Cook - Unit No.

2 10-10-78 B. A. Svensson 616 465-5901 SEPTEMBER, 1978 M-1 M-2 2CD Diesel Lube oil monthly sample indicated low viscosity.

Further investigation indicated that the lube oil was contaminated with fuel oil.

Drained oil, inspected for leaks, but found none.

Filled with new oil and test ran engine.

Containment air lock doors on 650'levation interlock did not work.

Adjusted interlocks and tested to ensure proper operation.

Vent Condenser for the South Rad-Waste Evaporator had a tube leak.

Cut CCW supply lines, removed tube bundle to locate and plug leak.

Reinstalled and welded CCW lines.

M-4 Check valve, MS-108-3, in line from Main Steam header to Turbine Driven Aux.

Feedpump was leaking.

Replaced a 3;" plug in top of the valve and returned to service.

M-6 H-7 M-8 ClaI-I CKI-2 CRI-3 Reactor Trip Breaker B closing coil was hot.

Linkage on closing coil relay had worked loose and was reinstalled and tested.

The shaft seal on 2CD Diesel "Before 8 After" lube oil pump was leaking.

Replaced entire pump.

Emergency boration valve, WHO-420 would not open al1 the way. 'is-assembled valve and found boric acid crystals on top of stem.

Cleaned out valve, reassembled, had limit switches adjusted and tested the valve satisfactorily.

2 AB Diesel,

~6 front bank starting air check valve stuck open.

Re-placed check valve and had engine run for functional test.

Hain turbine stop valve "D" would not test.

The solenoid coil on the stop valve "D" test circuit required replacement.

Radiation monitoring system channel R-19, steam generator blowdown sampling monitor failed.

The channels detector required replacement.

A detector channel calibration was performed on R-19.

The rod position indication for shutdown bank B rod C-9 indicated full scale.

The signal conditioning module drifted and was recal-ibrated.

The rod position and indication was verified prior to returning the instrument to normal service.

DOCKET NO.

UNIT NAME

,DATE COMPLETED BY TELEPHONE PAGE 50 - 316 D.

C.

Cook - Unit No.

2 0-10-78 B. A. Svensson 616 465-5901 MAJOR SAFETY-RELATED MAINTENANCE SEPTEMBER, 1978 The main turbine stop valve "C" closed limit switch arm was found loose.

The arms on the closed limit switch and RPS limit switch were replaced.

The arms were adjusted and the valve tested.

2PB-458A, pressurizer

pressure, high pressure reactor trip bistable failed.

The module was removed from service and replaced with a spare bistable.

The spare bistable was calibrated and the loop restored to a normal status; MRV-231, steam generator No.

3 stop valve dump valve, was leaking air.

The quick-release gasket of the valve required replacement.

Correct valve operation following the gasket replacement was verified.

The setpoint signal of 2TY-411L, loop 1 overtemperature delta T setpoint generator, indicated greater than loops 2, 3 and 4.

The instrument was found to have drifted high.

A spare module was placed into the pro-tection set loop and calibrated.

The cause of the instrument drift was determined as a cold solder joint on a zener diode in the main amplifier of the instrument.

The pressurizer pressure control setpoint indicated a downward. shift.

HRV-164, spray valve began opening at 2230 psig.

The setpoint of 2PK-455A, pressurizer pressure controller, was adjusted and the system maintained the correct pressure.

MRV-223 and MRV-233, steam generator power reliefs began to open in automatic mode when the pressure indicated 820 psig.

The electronic to pneumatic converters, EPT-223 and EPT-233, supplying air to the valve positioners required recalibration.

The solid state protection system train B failed to test correctly on logic switch A position three and four and on positions eleven and twelve of the permissive switch.

Universal logic card A-306 was re-placed.

A retest was performed to verify the operability.

Nuclear instrumentation system channels N31 and H32 source range were found energized while the reactor power level indicated 100".

During the trouble shooting and repair of the train B solid state protection system, train B was de-energized which resulted in de-energized relay K-629.

The de-energizing of K-629 restored the source range high voltage.

Logic test switch A and the memory test switch were po-sitioned to provide the proper logic to a

HAND gate which re-energized K-629 and de-energized the N31 and H32 high voltage.

~

~

~ i UNITSIIUTI)OWNS ANI)PO>VEI( ItEI)UCTIONS PORTMONTII August, 1978 (CORRECTED COPY DOCKET NO.

UNITNAME l)ATE COhlPLETEI) IlY TELEPIIONE 50-316 8

B.A. Sv nsson PAGE 1

OF 2 l)ale

~4'~

f) Jll LII:cost:c I:vent Itcpt)fl 4 LJC'I) p tl l)Eu p

CJ Cause 8t Ct)flet.'Ilvc Actiinl tt)

I ft.vcl'll ltct.t)flent.t.

30 31 32 33 780721 S

115.7 780805 F

6.2 32.8 3.8 780821 F

780823 F

N/A N/A N/A ZZ ZZZZZZ ZZ ZZZZZZ.

ZZ.

ZZZZZZ ZZ ZZZZZZ Outage continued from previous month.

Unit returned to service 780805.

Total outage time 359.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

Turbine/Generator tripped manually due to high vibration on Ho.

1 Bearing.

Reactor ttlaintained critical Reactor power returned to 90K 780806, and 99K 780807.

Unit trip.

Trip due to low condenser vacuum.

Unit trip due to high level in No.

1 steam generator when in manual contro.

during startup.

Reactor power re-turned to 98K 780823.

Reactor power at 100K for the first time on 780824.

(Continued on next page)

I': Foiccd S: Sclicdiilcil It)177)

Itcast)n:

A I'.ili)tplncnl Fallt rc (Explahl)

I)-heal))lena))cc or Test

('-Rcfttcllot, 0 Rcgtdtettt)fy Itcstrlcttt)t)

I: Oper't)tt)r Ifah)It)g Fir, Llt:cnsc I:xanlhlatllnl F-Ailnliolstrativc C Opcfallt)llal I:Ili)f(I:xp)al)))

II.Other (lixplahi)

Meth))d:

I.Maolial 2 hfanoal Scfaln.

3-At)ttnnat)c Scram.

4'Olhcf (Lxplaln) lixhlblt G - lnstriicllons fi)r Prcparatlo>> i)fl)ata bitry Shccts for l.lcc>>scc Event Rcpi)rt (l.liR)I'ilc(N(lltliG-Ol 6) I }

5

'lixhlblt I - Salnc Soorcc