ML20042C440

From kanterella
Jump to navigation Jump to search
Monthly Operating Rept for Dec 1981
ML20042C440
Person / Time
Site: Cook 
Issue date: 01/05/1982
From: Gillett W
INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML20042C427 List:
References
NUDOCS 8203310404
Download: ML20042C440 (8)


Text

-_

. OPERAT:NC DAT REPORT

~~

50-316 DCCKIT NO.

DATE _l-6-81 l

CO.stPLETID ;Y W T-M11ett D 16-4DD-5 WI g-, r3MONE cPERATING STATUS Donald C. Cook 2

Nous 1, ug, g, December 1980

2. ReponfsgPsc. d:

3391 o

3. U-HTE :=st?owerptWt):

1133

4. Nameolate Ran=3 (Csons ?.tWe): -

1100

3. Design Elec:i=1 R::ing (Nec MWe):

a l

6. "- d a = Dependable Cap = city (Cross MWe):
7. M=^-mn D

-~d-8 te C: pac::7 (Nec MWe):

. 8. If Changes Oc:nrin Capaci:y Rzri=gs (Iterns Numbar 3 Th:ough 7) Sinc = Last Report. Give R: sons:

-l 4

i

9. Powe Level To which Res====6 If Any (Nat MWe):

I

10. Reasons For F---d dans.lf Any:

l l

This Month Yrao-Dar?.

Cu=u!=tive d

744 8.784

'16 Ana.n II. Ecu:s != Repor:fsg Period 501.8 6.662.2 17.742.1

12. Nur.har of Hou:s R= cor Wss C:id=1 0

0 0

13. Re cer Reserve Shu:down Ho.s 469.4 6,538.0 17.039.6
14. Hours C- -m On L!n, 0

0 0

15. Unic R.: serve $*ausdown Hou:s 1,488,158 21,395,254 53,619.634 l
16. Cross The=n=1 E= rgy Ce===ted OtWH)
17. Cross Elec:ic=1 Energy Cen=2:sd G.!WH1 480.050__.,

6,937,420 17,091,830 462,782 6,691,753 16,459,165

11. Nec E!.=acal E: rgy Gener2:=d y.tWE) 63.1

/4.4

/1.o

}

19. Unic service Fsco, 63.1

/4.4 71.6 F

l

20. Unic Av..ilsh II.7 actor 57.5 70.4 66.4

!. Unit C.pacey F=cor(Using MDC Net) 56.5 69.5 65.7

. U=it Capacity is=:or(Using DER Nett 36.9 17.6 15.5 l
23. Unit Forc=d Cu: age Race
24. Shutdowns Scheduled Over Nex: 6 Months (Type. Date.:nd Du:: tion of I:ch3:
5. !! Shr
Dowr At End Of Report Period. Esti=: red Date of Scar:ue:

Force:st Achieved

. 25. Units is Test 5::rus iPnor o Ce==eecisi Oper::fon::

INITIA L CRITICAIJTY INITIAL Ets.. 5:C:n CO?.t.*.tERCIA:. 0PE?.A T:ON guf m 8203310404 820114 PDR ADOCK 05000316 R

PDR

^

~~

L-

AVERAGE DAILY UNIT POWER LEVEL l

i DOCKET NO.

50-316 UNIT 2

OATE 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) 17 1054 1

18 1073 2

19 1076 3

4 20 1067 5

21 1064 6

22 1065 7

23 1058 8

24 1063 9

25 Insa 10 51 26 Inso 11 771 27 1060 12 250 28 1064 13 809 29 1062 14 993 30 1046 15 31 Ings 16 481~

INSTRUCTIONS On this fomat list the. average daily unit power level in MWe-Net for each day in the reporting month._ Compute to the nearest whole megawatt.

r v

e-w,-wehe

--w=.m.-..... -,

- - = -, - ~

  • -. - +

l 50 - 316 DOCKET NO.

UNITSilUTI) OWNS AND POWER REDUCTIONS D.C. Cook - Unit 2 UNIT N AnlE l-14-81 DATE 6.A. Svensson December, 1980

  • COMPLETED BY REPORT MONTil TELEPilONE (616) 465-5901 PAGE 1 of 2 w

o a

Licensee h

$4 Cause & Conective

,$g 3

) s$5 5

Event gg pU Actiam to No.

Date g;

Eg 5

Prevent Recurrence yI, y

g l{epor #

to O H

g 6

I 89 801018 F

234.3 A

3 N.A.

HA GENERA The generator repair outage continued Cont'd.

from the previous month.

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

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

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

/ Continued.

I 2

3 4

F: Fmcetl Reason:

Meilunl:

Exhible G - Insinicilons S. Schetlulcil A-Equipmens Failure (Explain) 1-Manual for Piepasation of Data ll Maintenance of Test 2 Manual Scram.

Entry Sheets for I.icensee C Refueling

3. Automatic Scram.

Eveni Reposi (l.E R) File INURI G-D Ilegnisimy Resiticelun 4-Other (Explain) 0161)

E-Operator l'ealning & I_icense lixaminallon F Administ ative 5

G Operational Liner (Explaini lixhibit I - Same Somce t'l/77)

Il-Other (Explaini

I DOCKET NO.

50 - 316 UNITSilUTDOWNS AND POWER REDUCTIONS D.C. I;ook - Unit 2 UNIT NAME l-14-81 DATE COMPLETED HY B.A. Svensson DECEMBER, 1980 REPORT MONT11 TELEPilONE (616) 465-5901 PAGE 2 of 2 "t.

s.

O c:

Licensee

,E t, je.,

Cause A Conective 3p 3

}Y5 g,E Event g '[F pU Action to 3 ij s

No.

Date g

Pievent Hecussence y$

g$

Heport #

MU H

g

\\

6 l

l 91 801214 F

28.2 A

3 N.A.

HA GENERA The unit tripped from 100% power due l

to loss of generator excitation. The reactor trip was initiated by the reactor coolant pump bus undervoltage relays and wac 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 nas not been determined. The unit was re-turned to service on 801216 and brought to 100% power on 801217.

I i

1 2

3 4

F: Forceti Heason:

Metinal:

Enliible G-Instructions S: Scliciluicil A Equipmens Failme(Explain) 1 Manual for Preparation of Data ll-Maintenance of Test 2 Manual Scram.

Eni y Sliceis fm 1.icensee C Refueling 3 Automatic Scram.

Eveni Repose ti.ERI File INURI:G-j D Regniatiny Restricilon 4 Other (Explain) 01611 E-Operator l'saining & License lixaminallon F Ailministrative 5

G Operational Enor IExplain) lixliihin 1 Same Somce 19/77) 11 Other (Explain)

~

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-fled 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 tne Summary.

Total electrical generation for the month 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.

The East Containment Spray Pump was inoperable for a 9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 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 <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period to repair a problem in the Trip and Throttle Valve Control Circuit.

12/08/80 - At 0847, manually tripped the Reactor during planned 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 <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period to repair a steam leak.

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

12/11/80 - The Containment Radiation Monitor R-11 was inoperable for a 9 hour1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 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 i

l Sunmary:

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 l

1 paralleled at 1643. The Unit was loaded to 100%

at 1720 on 12-13-80, 12/14/80 - At 2218, the Unit tripped from 100% power. The l

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 <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> 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 <br />8.333333e-4 hours <br />4.960317e-6 weeks <br />1.1415e-6 months <br /> 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 <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> 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 <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period to change oil.

12/19/80 - The East Component Coolirig Water Pump was inoperable for a 1.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> 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 perform 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 <br />0.00694 hours <br />4.133598e-5 weeks <br />9.5125e-6 months <br /> period to change oil.

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

DOCKET N0.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 1-14-81 COMPLETED BY B. A. Svensson 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 rejected 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 assembly 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 operatier, was verified.

DOCKET N0.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE l-14-81 COMPLETED DY B. A. Svensson TELEPHONE 1616)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 temperature 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 automat'c 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.

-