Text

Monthly Operating Rept for Feb 1980
	ML20050B883
Person / Time
Site:	Cook
Issue date:	03/05/1980
From:	Gillett W; INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:	;
Shared Package
ML20050B879	List: ML20050B878; ML20050B883;
References
	NUDOCS 8204070518
	Download: ML20050B883 (10)
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l OPERATLN,G DATA REPORT DOCFl!NO. 50-316 DATE 3 A0 COMPLETED P.y W T r,ill ett -

TELEP.90NE. 616-465-590I O?EFAT!NG STATUS Donald C. Cook 2

Not"

1. Unic N.me:

February 1980

2. Reporting Period:

3391

3. LI:ensedRe:ms!Powee(MW:):

1133

4. Namepist: Ratin;(Gross MW:):

1100 S. Design Ele::ri=1 R::ing (Ne: MWe):

III8

6. Maximum Dependsble Capsci:'f (Gross MWe):

1082 T. Maxi =um Dependsble C:pecity (Net MWe):

S. If Ch:n;es Oc:arin Capad:y R2 tings (Items Numb:: 3 Through 7) Sine: Last Report. Give R:2 sons:

~

e

9. Power Level To Which Res::ic::d,If Ar:y (Net MWe):

10. Reasons For R:s::i::fons.If Any:

His Month Yr to.Dat-Cumt!:tive lle g b$ & 3 Z ey p

696 1440 18,960

!! Hou s in Repor:in Period 680.6 1001.4 12,081.3

12. Nurnber Of Hours Reactor Was Cri:ica!

U O

13. Resc:or Reserve Shu:down Hous 670.3 921.0 11,422.9

14. Hours Genemtor On.Line 0

0 0

15. Unic R: serve Shutdown Ho s

16. Gross The.ms! E : rgy Genemted (MWH)

M C 3^3 LMAROP

_-E-O' ^ : ' 7 714,670 897.420 11.051.830

17. Gross Ele ::ie:1 Ener;y Gener::ed (MWH) 689,185 863,137 10,630,549 IS. Net Ele:: rim! Ener:y Genem: d C.tWH) 96.3 64.0 69.1

19. Unit Servi:: Fsetor 96.3 64.0 69.1

20. Unit Av:ilabill:y F:ctor 91.7 55.5 62.9

21. Unit C:pacity F:ctor (Usin: MDC Net) 90.U 54.5 61.8

22. Unit Capseity Fse:or (Using DER Net) 3.7 2.7 13.0

23. Unic For::d Ou: g: Rat,

24. Shutdowns Scheduled Over Nex: 6 Mon:hs (Type.Date.:nd Durstion of Each1:

25. If Sht: Down At End Of Report Pe-iod. Estim:ted Date of Startup:

25. Units la Test Sts:us (Prior to Cemme-cial 0;:=tioni:

Force:st Achieved INIT!A L CRITICALITY INITIA L ELECTR:C;TY COM.*.;ERCIAL OPER ATION e,m i 8204070518 900306 PDR ADOCK 05000316 R

PDR i

AVERAGE DAILY UNIT POWER LEVEL DOCKET N0.

50-316 UNIT 2

DATE 3-4-80 COMPLETED BY W. T. Gillett TELEPHONE 616-465-5901 MONTH February 1980 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)

(MWe-Net) 4 1

107a 17 inR2 2

1088 18 1084 3

948 19 414 4

1080 20 1089 5

1092 21 1096 6

1091 22 1089 7

1092 23 1074 8

1091

.24 1079 9

977 25 1082 10 933 26 431 11 1090 27 1090 12 442 28 1077 13 930 29

'1092 14 867 11 15 1072 W

16 1066

-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.

3

DOCKET No. 50-316 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT N AME D.C. Cook-Unit 2 DATE 3-6-80 COMPLETED ily B.A. Svensson REPORT AIONTil February, 1980 TELEPilONE (616) 465-5901 PAGE 1 of 2 I

r.

jg 3

y Licensee g-r,,

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cause & Correceive No.

Date Q

Eg s

jsE Event g,7 93 Action to

}U fE j ;f, Report a mO Preveni Recurrence H

c5 68 800203 5

0 B

4 N.A.

ZZ ZZZZZZ' Reactor power reduced to 80% to per-form power coefficient test.

Reactor power returned to 100% 800204.

l 69 800210 S

0 B

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 75% for turbine and moisture separator re-heater performance testing.

Reactor power returned to 100% the same day.

70 800212 F

10.6 3

N.A.

HA XXXXXX Turbine / Reactor trip due to extreme high level in left moisture separator reheater.

Spurious trip - no evi-dence of high level in the moisture separator.

Unit returned to service the same day.

Reactor power at 100%

800213.

71 800213 F

0 H

4 N.A.

ZZ ZZZZZZ Reactor power reduced to 60% due to secondary side water chemistry problems to enhance cleanup. Re-actor power returned to 100% 800214.

(Continued On Next Page)

I 2

3 4

F: Forced Reason:

Method:

Exhibii G - Inst ructions S: Sclieduled A-Equipment Failme(i.xplain) 1-Manual for Preparation ol Data ll. Maintenance of Test 2 Manual Scram.

lintsy Sheets for I.icensee C. Refueling

3. Automatic Scram.

Event Report (l.I'll) Fde INUltin D Regulatory llestriction 4 Other (Explain) 01611 E-Operator l' raining & License lixamination F-Administrative 5

G. Operational Enor (Explain)

Exhibit 1 - Same Sonice 19/77)

II Other (Explain)

UNIT SilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-316 UNIT N AM E D.C. Conk-tinit 2 DATE 3-6-80 COMPLETED IlY B.A Svensson REPORT MONTil Februarv. 1980 TELEPIIONE (616) 465-5901 PAGE 2 of 2 3E

}

Y Licensee

,E g Cause & Conneclive No.

Date g,

gg g

jg5 Event g7 el Actiim to f I.,

5 3 ;5 g Repor #

m' O E'

Prevent Itecurrence H

e o

Q 72 800219 F

8.4 H

2 N.A.

HA ZZZZZZ Unit tripped manually due to high vibration on No. 4 turbine bearing.

The high vibration is believed to have been caused by rapid tempera-ture change while placing moisture separator reheater in service.

Unit returned to service and reactor power reached 100% the same day.

73 800226 F

6.7 G

1 N.A.

ZZ ZZZZZZ Unit removed from service due to high vibration on turbine generator bearing No. 5.

Vibration believed to be caused by rapid temperature change in generator gas temperatures caused by operational error.

Unit returned to service the same day.

Reactor power at 100% 800227.

i 2

3 l

F: Foiced Iteason:

Method:

Exhibit G -Instructions S: Scheduled A Eiluipment Failme(I.xplain) 1 Manual for Pseparation of Data ll4taintenance or' Test 2 Manual Scram.

Entry Sheels for 1.icensee C Refueling 3 Autinnatic Scram.

Event Report (1.ER) File (NURIL D Regulatiny Restriction 1-Ot hei (Explain) 0161)

E Operator l' raining & License Examination F-Administrative 5

19/77) ~

G.Opciational Einor (Explain)

Exinbit I Same Somce Il-Ot her (Explain)

Docket No.:

50-316 Unit Name:

D. C. Cook Unit #2 Completed By:

R. S. Lease Telephone:

(616) 465-5901 Date:

March 11, 1980 Page:

1 of 4 l MONTHLY OPERATING EXPERIENCES -- FEBRUARY,1980 l l Highlights l :

The L' nit entered the reporting period operating at 100% power.

The Reactor / Turbine Generator was out of service two separate occasions during the reporting period as detailed in the sumary.

One other time the Turbine Generator was out of service, but the Reactor remained critical. This is also detailed in the summary.

Total electrical generation for the month was 714,670 Mwh.

lSummaryI:

2/1/80 -- The West Centrifugal Charging pump was inoperable for a 6 hour6.944444e-5 days 0.00167 hours 9.920635e-6 weeks 2.283e-6 months period for required maintenance work.

2/3/80 -- Power was reduced to 80% over a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at C600. This was for Power Coefficient testing.

Power was returned to 100% over a 5.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months ramp starting at 1855 hours0.0215 days 0.515 hours 0.00307 weeks 7.058275e-4 months 2-3-80.

2/4/80 -- The North Safety Injection pump was inoperable for a 2 hour2.314815e-5 days 5.555556e-4 hours 3.306878e-6 weeks 7.61e-7 months period for inspection of a safety valve.

The East Residual Heat Exchanger was out of service for a 12.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period for repair of a safety valve.

2/5/80 -- Steam Generator No.3 Level Channel I was inoperable for a 3 hour3.472222e-5 days 8.333333e-4 hours 4.960317e-6 weeks 1.1415e-6 months period for necessary repairs.

The No.3 Boric Acid Transfer Pump was removed from service at 1150 hours0.0133 days 0.319 hours 0.0019 weeks 4.37575e-4 months for replacement of.the pump seal. This pump was returned to operable status at 1514 hours0.0175 days 0.421 hours 0.0025 weeks 5.76077e-4 months 2-8-80.

2/6/80 -- The Turbine Drive Auxiliary Feedwater pump was in-operable for a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months period while the tip from a hand-held tachometer was removed from the outboard pump bearing housing.

i l-

Docket No,:

50-316 l

Unit Name; D, C. Cook Unit #2 l

Completed By:

R. S. Lease Telephone:

(616) 465-5901 Date:

March 11, 1980 Page:

2 of 4 2/6/80 -- The APDMS system was inoperable for a 5.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period (cont'd) for necessary repairs.

2/8/80 -- Steam Generator No. 23 Level Channel I was inoperable for an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period for necessary repairs.

2/9/80 -- Power was reduced to 85% over a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ramp starting at 0500 hours0.00579 days 0.139 hours 8.267196e-4 weeks 1.9025e-4 months . This was for Turbine Efficiency testing. Power was returned to 100% by 2132 hours0.0247 days 0.592 hours 0.00353 weeks 8.11226e-4 months .

2/10/80 -- Power was reduced to 75% over a 1.5 hour5.787037e-5 days 0.00139 hours 8.267196e-6 weeks 1.9025e-6 months period.

This was again for Turbine Efficiency Testing.

Power was returned to 100% by 2000 hours0.0231 days 0.556 hours 0.00331 weeks 7.61e-4 months .

2/11/80 -- The West Residual Heat Removal pump was inoperable for a 33 hour3.819444e-4 days 0.00917 hours 5.456349e-5 weeks 1.25565e-5 months period starting at 0630 hours0.00729 days 0.175 hours 0.00104 weeks 2.39715e-4 months for re-packing of a valve.

2/12/80 -- The Unit and Reactor tripped from 100% power at 0814 hours0.00942 days 0.226 hours 0.00135 weeks 3.09727e-4 months , The trip was caused by an extreme high level in the Left Moisture Separator Reheater.

The trip appears to have been spurious since there was no evidence that a high level actually existed. The Reactor was returned to critical at 1726 hours0.02 days 0.479 hours 0.00285 weeks 6.56743e-4 months and the Generator was paralleled to the system at 1849 hours0.0214 days 0.514 hours 0.00306 weeks 7.035445e-4 months . The Unit was loaded to 100% power by 1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months 2-13-80.

2/13/80 -- Power was reduced to 60% over a 1 hour1.157407e-5 days 2.777778e-4 hours 1.653439e-6 weeks 3.805e-7 months ramp starting at 2308 hours0.0267 days 0.641 hours 0.00382 weeks 8.78194e-4 months due to high conductivity in the Condensate and Feedwater system. The excessive conductivity had been traced to a large leak in the South half of the

'A' Condenser.

By this time, the leak had been isolated, but the power reduction was taken for more effective clean-up.

l 2/14/80 -- The Unit was loaded to 100% power between 0805 and 1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months , l

Containment Radiation Monitors R-11 and R-12 were I

inoperable for a 10 hour1.157407e-4 days 0.00278 hours 1.653439e-5 weeks 3.805e-6 months period because the sample pumps would not run, The West Residual Heat Removal pump was inoperable for a 9 hour1.041667e-4 days 0.0025 hours 1.488095e-5 weeks 3.4245e-6 months period while a valve was repacked.

)

Docket No.:

50-316 Unit Name:

D. C. Cook Unit #2 Completed By:

R. S. Lease Telephone:

(616)465-5901 Date:

March 11, 1980 Page:

3 of 4 2/15/80 -- Safeguards Fan HV-AES-2 was inoperable for a 5.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for inspection.

2/16/80 -- Containment Recirculating Fan CEQ-2 was inoperable for a 11.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for repair to the suction damper.

2/19/80 -- Power was reduced to 90% starting at 0030 hours3.472222e-4 days 0.00833 hours 4.960317e-5 weeks 1.1415e-5 months .

This was in preparation of placing reheater coils in service.

shile placing the reheater coils in service, Turbine Bearing No.4 vibration started increasing from a normal 2 mils. When this vib-ration reached 9.5 mils, the decision was made to trip the Unit and the Reactor trip breakers were open at 0250 hours0.00289 days 0.0694 hours 4.133598e-4 weeks 9.5125e-5 months . The Reactor and Turbine tripped, but the Generator continued to motor due to a failed Turbine valve limit switch.

The Generator Output Breakers were manually opened at 0255 hours0.00295 days 0.0708 hours 4.21627e-4 weeks 9.70275e-5 months . This initiated black-out conditions on the Unit and both Emergency Diesel Generators started and accepted their designated load.

The Unit was returned to nonnal electrical con-figuration by 0330 hours0.00382 days 0.0917 hours 5.456349e-4 weeks 1.25565e-4 months .

The Reactor was returned to criticality at 0905 hours0.0105 days 0.251 hours 0.0015 weeks 3.443525e-4 months and the Unit was paralleled to the system at 1118 hours0.0129 days 0.311 hours 0.00185 weeks 4.25399e-4 months .

The Unit was loaded to 100% power by 2320 hours0.0269 days 0.644 hours 0.00384 weeks 8.8276e-4 months .

The vibration pattern of No.4 Turbine Bearing was normal during start-up_and loading.

2/21/80 -- Containment Radiation Monitor R-11 was inoperable for a 5.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period for calibration.

Stack Radiation Monitor R-25 was inoperable for a 5.25 hour2.893519e-4 days 0.00694 hours 4.133598e-5 weeks 9.5125e-6 months period for repair of.the check source.

2/22/80 -- Stack Radiation Monitor R-11 was inoperable for a 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months period to repair the filter drive.

2/23/80 -- The Turbine Efficiency test was from 100% power with Tavg reduced 8.

2/25/80 --

Icing conditions on the Circulating Water Intake Screens caused reduced Circulating Water flow.

~

Docket No.:

50-316 Unit Name:

D. C. Cook Unit #2 Completed By:

R. S. Lease Telephone:

(616) 465-5901 Date:

March 11,1980 Page:

4 of 4 2/25/80 -- This resulted in higher than normal Generator (cont'd) temperatures due to the effect on the Generator Cooling Systems.

This condition started at 2130 hours0.0247 days 0.592 hours 0.00352 weeks 8.10465e-4 months and lasted for approximately 20 minutes.

The higher than normal generator temperature apparently effected the vibration of the No.5 Turbine Bearing and it started increasing from a normal 5 mils.

2/26/80 -- At 0115 hours0.00133 days 0.0319 hours 1.901455e-4 weeks 4.37575e-5 months the vibration in No.5 Bearing had increased to 10.3 mils. The Unit was then unloaded to 62% and during the unloading the vibration increased to 11.2 mils.

The Unit was further unloaded and removed from service at 0444 hours0.00514 days 0.123 hours 7.34127e-4 weeks 1.68942e-4 months . The Turbine was placed on the turning gear while the Reactor remained critical at less than 10% power. The Unit was re-rolled at 1016 hours0.0118 days 0.282 hours 0.00168 weeks 3.86588e-4 months and paralleled with the system at 1124 hours0.013 days 0.312 hours 0.00186 weeks 4.27682e-4 months .

The Unit was loaded to 100%

power by 0025 2-27-80. During the roll-up and loading the No.5 Bearing vibration was normal.

2/28/80 -- The East Centrifugal Charging pump was out of service for an 8 hour9.259259e-5 days 0.00222 hours 1.322751e-5 weeks 3.044e-6 months period for required main-tenance.

Contair. ment Radiation Monitors R-11 and R-12 were inoperable for a 7 hour8.101852e-5 days 0.00194 hours 1.157407e-5 weeks 2.6635e-6 months period for repair to the sample pumps.

2/29/80 -- Containment Radiation Monitors R-11 and R-12 were inoperable for a 29.75 hour8.680556e-4 days 0.0208 hours 1.240079e-4 weeks 2.85375e-5 months period starting at 0947 due to filter drive failure.

This Unit experienced its normal Condenser tube leak problems and Condenser Halfs were out of service periodically throughout the reporting period.

DOCKET N0.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 3-6-80 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 2 MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1980 M-1 The emergency boration line motor operated isolation valve, QM0-402, would not close. A wire was found to be interfering with the close torque switch. Wire was rerouted and valve tested.

M-2 The CD emergency diesel rear jacket water manifold was leaking.

Re-placed jacket water outlet gaskets.

Had engine tested.

M-3 The east RHR heat exchanger discharge safety valve, SV-104, leaked when another safety valve discharging to the common header lifted.

The leakage vss the result of ruptured bellows.

The bellows were replaced.

M-4 RHR heat exchanger bypass valve, IM0-324, had a packing leak and valve would not operate manually.

Replaced bevel gear in limitorque, repacked valve and had it tested.

M-5 The HEPA filter for ESF ventilation system fan HV-AES-2, had a high DP.

Replaced HEPA filter and had unit tested.

M-6 Ventilation damper VM0-102 for the containment equalization fan, HV-CEQ-2, would not operate.

Replaced contactor in motor control center and had damper tested.

C&I-l ZRV-020, the fire protection water supply to the 2-HV-CPR-1, contain-ment pressure relief ventilation unit would not open. The circuit board was replaced and operability test was performed to verify correct operation.

C&I-2 The test solenoid for main turbine control valve "B" was preventing the cycling of the valve. A broken lead was found on the terminal strip of the solenoid. The wire was repaired and reterminated.

C&I-3 The proximity switch on stop valve "B" supplying a trip signal to the solid state protection system would not respond. The switch had vibrated loose from the mounting plate and was suspended by the leads.

The proximity switch was remounted and verified operational.

C&I-4 Main turbine stop valve "B" test solenoid failed.

The solenoid was replaced with a spare solenoid. A functional test was per-formed on the operation of stop valve "B".

i l

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DOCKET N0.

50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 3-6-80 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 2 MAJOR SAFETY-RELATED MAINTENANCE FEBRUARY, 1980 C&I-5 The closed limit switch on the main turbine stop valve "B"

failed.

The switch actuation arm had vibrated off the limit switch shaft.

Inspection of the actuation arm revealed that the arm's spline had been worn, allowing free movement of the actuation arm and not actuating the switch.

The arm was replaced with a spare and a functional test was performed.

C&I-6 Steam generator number 3 level transmitter BLP-131, was cycling from 40% to 48% level indication.

The transmitter was replaced.

The new transmitter was calibrated and placed in service.

C&I-7 The limit switch on "B" stop valve was found to have a stripped splined shaft and actuating lever.

The required parts were re-placed. The stop valve was stroked to verify proper operation of its limit switch.

C&I-8 Feed flow transmitter FFC-231, was giving a low indication.

Re-calibration of the transmitter restored proper operation.

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ML20050B883

Text

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