Text

Monthly Operating Rept for Dec 1980
	ML20066D481
Person / Time
Site:	Cook
Issue date:	01/05/1981
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML20066D469	List: ML20066D467; ML20066D481;
References
	NUDOCS 8211110362
	Download: ML20066D481 (8)
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OPERATING DATA R.EPORT 50'316

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DOC 1~IT NO.

DATI l-6-81 C05tPLETED SY W.T M11ott 61o-406-5901 T" **.5f CN3 OPERATING STATUS Donald C. Cook 2

N* *:8

1. Unic Mine:

December 1980

2. Reporting Pe=. d:

3391 o

3. U~ Mns=21 Power @ twt):

1133

4. Na:nepiz = Rsc=g (Cross LDve):

1100

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5. Design Ele==i=1 R::ing (Nec MWe):

6. h Dependshie Csynchy (Cross SIWE):

7. Ma.nc= n D -- d-5 I-CM (Nec 31We):

S If Changes Oc:arin Capaci:7 P'd gs (It=ms Nu=sbar 3 Through 7) Sinca Last Repor-Cive Resons-

9. Powe L.-vel To Whl=h Ras -L =d,If Any (Nec SUVe):

10. R== sons For P s dans.If.W:

This Month

' Yrao.Date.

C # -dve 744 8.784 76 Ana.n

11. Hon:s In Repor:ing Period 501.8 6.662._2 17.742.1

12. Nu=herCf Enc:s R=.=:or W2s Cric I 0

0 0

13. Rec:or Rese:ve Shu::iewn He.::s 469.4 6,538.0 17.039.6

14. Hea:s C-me on.L*n, 0

0 0

15. U=ir R-se:se S~ncedown Ecc:s 1,488,I C 21,395,254 53,619,634

16. Cross The=s:1 E..===y Cee=:=d (5tWH)

17. Cross E!e==ic=! E===gy Gener: d @!WE) 480.050,_,

6,937,420 17,091,830 462,782 6,691,753_

16,459,165

18. Ne IIe==ic=1 r-- ;y Cee s ptwE) 63.1 74.4

/1.o

19. U::it Servie= Psc:or 63.1

/4.4 71.6

20. Unit AniIsailI:r F=ctor 57.5 70.4 66.4

21. Unit C:pse=y 7:c:ar (IIsing M.DC Nec) 56.5 69.5 65.7

22. U it capacity. s=or (Using DER Nett 36.9 17.6 15.5

23. Uni: For==d ou:sge Race

24. Shu: downs Schedu!ed Over Lx: 6 Moa:hs(Type. Date.:ad Dur::. ion of E:ch1:

9

S. !!jih:: Down At Isd Of Report F=riod. Esti==:ed Date of Scar:up:.

. 25. Units is Test Sc:::-i IPnor io Ce==er=ist Oper:: ions:

eorec=st ~

Achieved INITIA L CRIT CALITY

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INITIA L EL:<. i..:C;-'Y CO 4:4ERCIA:. OPE? G10N 1

F211110362 810114 F

'"3 PDR ADOCK 05000316 s

R PDR V

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AVERAGE DAILY UNIT POWER LEVEL

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DOCKET tiO.

50-316 UNIT 2

DATE 1-5-81 COMPLETED BY W. T. Gillett TELEPHONE (616) 465-5901 MONTH December 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 1 17 1054 2

18 1073 3

19 1076 4

20 1067 5

21 1064 6

22 1065 7

23 1058 8

24 1063 9

25 1n53 10 51 26 1nso 11 773 27 1060 12 250 28 1064 13 809 29 1062 14 993 30 ina6 15 31 inn 16 481 INSTRUCTIONS On this fonnat list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

s.

UNITSilUTDOWNS AND POWER REDUCTIONS I)OCKET NO.

50 - 316 5

UNIT NAME D.C. Cook - Unit 2 DATE - l-34-81

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December,1980 COMPLETEu lly B.A. Svensson i

REPORT MONTil TELEPilONE (616) 465-5901 1

i PAGE 1 of 2 I

"L.

I w

c

,E g

}

. }

Licensee

,Eg g1, g

Cause & Correceive l

No..

Dale g;

gg

Q

.c a oc livent g,?

g{

Acilon su H

aE j iy, g Repor #

in U Preveni Reenstence f

89 801018 F

234.3 A

3 N.A.

HA GENERA The generator repair outage continued Cont'd.

from the previous month. The reactor j

was brought critical on 801207. The unit was returned to service on 801210 and brought to 100%' power on 801211.

j Total duration of outage 1270.3 hours3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months .

i 4

90 801212 F

12.1 H

3 N.A.

ZZ ZZZZZZ Turbine / Reactor trip. The turbine trip was caused by low condenser vac-uum. Condenser tube leakage repairs j

were in progress and the low vacuum condition resulted when removing a j

i loose tube plug at a location where the tube had previously been removed.

The unit was returned to service the same day.

100% reactor power was reached on 801213.

i

/ Continued...........

I 2

3 4

F: Forecil Reason:

Methoil:

Exhible G. Instrucittms i

S: Scheilnical A Equipniens Failure (Laplain) 1 Manual for Preparasion of Data I

in-Maintenance of Test 2 Manual Scram.

lintry Sliccis for I.icensee C Refueling 3 Automalle Scram.

Eveni Report (l.I!R) File INURl!G-D.Regulatiny Restricilon 4-Other (Explain) 01611 li Operator Training & License lixaminallnn i

F-Aihninistrative 5

G Operational Enor IExplain) lixhible 1 Same Sonice 19/77) ll-Other (Explain)

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50 - 316 DOCKET NO.

UNITSilUTDOWNS AND POWER REI)UCTIONS D.C. Cook - Unit 2 UNIT N AME DATE l-34-81 REPORT MONT11 DECEMBER, 1980 COMPLETED BY 8.A. Svensson TELEPilONE (616) 465-5901 PAGE 2 of 2 "t.c c

,E E

}

Licensee Eg h

Cause & Correcilve No.

Date h

Eg

,, ce Event g,7 g3 Acilunto AE 5

j;gg iteping #

un U O

Preveni Reentrence 6--

g 6

91 801214 F

28.2 A

3 N.A.

HA GENERA The unit tripped from 100% power due to loss of generator excitation. The reactor trip was initiated by the reactor coolant pump bus undervoltage relays and was followed by blackout, start-up of the emergency diesel gen-erators and load sequencing. The loss of excitation was caused by a failure of the pilot exciter which was found on fire. The exact reason for the pilot exciter fire has not been determined. The unit was re-turned to service on 801216 and brought to 100% power on 801217.

}

l 2

3 4

F: Finced Iteason:

Meilual:

Enliible G Inserncilons S: Sclicilulcil A Eiluipment Failure (Explain)

1. Manual for Preparation oI Data ll. Maintenance of Test

2. Manual Scram.

Entry Shecis fin 1.icensee C-Refueling 3 Automatic Scram.

Event Report (i.l:R) File INtlREG-D-Itegulaimy Restriction

-l Other (Explain) 0161)

II Operator l~ raining & License lixaminallon F Adminisiralive 5

G-Operational Enor (Explain) lixhibli ! Same Somce l'f/77)

Il Olher (limplain) i

1 Docket No.:

50-316 Unit Name:

D. C. Cook Unit #2 Completed By:

C. E. Murphy Telephone:

(616)465-5901 Date: January 14, 1981 Page:

1 of,2 MONTHLY OPERATING ACTIVITIES - DECEMBER, 1980 Highlights:

The Unit entered this reporting period in Mode 5 in the progress of running the Reactor Coolant Pumps and venting the Reactor Coolant System. The Unit had tripped from 100% power at 2057, Saturday, October 18, 1980. The cause of the trip was identi-fied as a ground in the Main Turbine Generator.

The Unit reached 100% power at 1925, Thursday, December 11, 1980.

There were three outages of the Reactor and Turbine Generator Unit during the reporting period. This is detailed in the Summary.

Total electrical generation for the Inonth was 480,050 mwh.

Sumary:

12/04/80 - The Source Range N-32 was returned to service at 0730 on December 4, 1980. This was removed from service at 1158 on November 25, 1980 to replace the detector.

l l

The East Containment Spray Pump was inoperable for a 9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months period to repair a leak on an instrument line.

12/06/80 - The Turbine Driven Auxiliary Feed Pump was inoperable for a 5.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period to repair a problem in the Trip and Throttle Valve Control Circuit.

12/08/80 - At 0847, manually tripped the Reactor during planned l

shutdown from low speed generator testing when it was discovered, there was no indicated bank over-lap between D & C Control Banks. The bank overlap was repaired at 2015.

The Turbine Driven Auxiliary Feed Pump was inoperable for a 2.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period to repair a steam leak.

12/09/80 - The North Control Room Air Handling package was inoper-able for a 12 hour1.388889e-4 days 0.00333 hours 1.984127e-5 weeks 4.566e-6 months period for a breaker inspection.

1 12/11/80 - The Containment Radiation Monitor R-11 was inoperable for a 9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months period to check the alarm setpoint.

l

Docket No.:

50-316 Unit Name:

D. C. Cook Unit #2 Completed By:

C. E. Murphy Telephone:

(616)465-5901 Date:

January 14, 1981 Page:

2 of 2 Sumary:

12/12/80 - At 0427, the Unit tripped from 100% power due to Low Vacuum in "C" Condenser. Tube leakage repairs were in progress in "C" South Condenser.

The Reactor was critical at 1436, and the Generator paralleled at 1643. The Unit was loaded to 100%

dt 1720 on 12-13-80.

12/14/80 - At 2218, the Unit tripped from 100% power. The trip was caused by a loss of field excitation which was a result of a fire at the Pilot Exciter. The trip was accompanied with an Emergency Bus Blackout and both Diesels running. The Emergency Buses were returned to normal reserve power at 2305.

The Reactor was critical at 0104 on 12-16-80 and the Generator paralleled at 0230. The Unit was loaded to 100% by 0500, on 12-17-80.

12/16/80 - The "E" Component Cooling Water Pump was inoperable for a 27 hour3.125e-4 days 0.0075 hours 4.464286e-5 weeks 1.02735e-5 months period due to a Low Flow on Lubricating Oil.

The "W" Motor Driven Auxiliary Feedwater Pump was inoperable for a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months period to replace a suction gasket.

R-25 and R-26, the Vent Stack Monitors were inoper-able for a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months period to adjust the paper drive.

12/18/80 - The West Component Cooling Water Pump was inoperable for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to change oil.

12/19/80 - The East Component Cooling Water Pump was inoperable for a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period to change oil.

12/20/80 - At 1138 the Reactor power was reduced to 97% to place the Moisture Separator / Reheaters in service for testing.- Reactor Power was returned to 100% at 1220.

The MSR Testing was completed at 1847 and they were removed from service at 1952.

12/30/80 - At 0840 the Reactor power was lowered to 90% to perfonn a Moderator Temperature Coefficient Evaluation. The Reactor power was returned to 100% at 1613.

The "W" RHR pump was inoperable for a 3.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period to change oil.

The "E" RHR pump was inoperable for a 1.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period to change oil.

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE l-14-81 COMPLETED BY B. A. Svensson 4

TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE DECEMBER,1980 M-1 The studs and nuts from the flanges of the auxiliary feedpump tur-bine trip and throttle valves were removed. Non-destructive exam-inations of the studs and nuts were performed. All rejectec items were replaced.

M-2 A socket weld on the 1" line to the east CTS pump discharge pressure instrument, IPA-210 was leaking. The pipe was removed from the socket, cut and rewelded. All necessary NDE was performed.

M-3 The east motor driven auxiliary feedpump emergency leak-off line safety valve, SV-141 was leaking by.

Lapped the seat and disc.

Valve was tested and reinstalled.

M-4 The boric acid blender outlet valve, CS-386 was leaking.

Replaced the valve diaphragm.

M-5 Replaced damaged valve stem / bonnet assenbly on R-158, glycol iso-lation valve, VCR-21 bypass. The system was refilled, valve operated properly.

M-6 The north suction strainer on the west motor driven auxiliary feedpump was leaking.

Replaced the gasket.

M-7 The east component cooling water pump outboard bearing had very little oil flow. The bearing end cap spiral passage was not passing enough flow.

Replaced the end cap. Tested satisfactorily.

M-8 The 2CD diesel bypass lube oil pump motor was grounded.

Replaced the motor. Tested satisfactorily.

C&I-l Solid state protection system, Train A, test point P-10 gave im-proper indication. A defective universal circuit board in the A 412 location was replaced. The SSPS Train A was checked by performing the logic surveillance.

C&I-2 Protection channel 2, steam generator No.1 level transmitter

- BLP-lll failed high.

Both sensing lines to the transmitter were found to contain sediment. After blowing out the lines and re-filling them with deionized water, proper operation was verified.

____________A

DOCKET NO.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE T 14-81 COMFLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE DECEMBER,1980 C&I-3 Pressurizer pressure indicators, NPP-152 and NPP-153 had a 20.PSIG difference in pressure. Pressure transmitter NPP-151, NPP-153 and NPS-153 were found to be out of calibration and were recalibrated.

Pressurizer pressure readings then returned to correct values on the above indicators.

C&I-4 The letdown heat exchanger teaperature control valve, CRV-470 would not function in automatic operation. The calibration of EPT-470 was found to be out of specification.

EPT-470 was recalibrated and the control system was placed into the automatic mode. The system maintained the correct temperature.

C&I-5 NR-42, nuclear instrumentation system power range, N43 upper detec-tor flux recorder failed. The recorders servo motor and feedback potenteometer were replaced. The recorder was calibrated and re-turned to service.

e 6

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ML20066D481

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