ML19347C922

Monthly Operating Rept for Jan 1981

ML19347C922
Person / Time
Site:	Cook
Issue date:	02/12/1981
From:	Campbell D, Svensson B, Tetzlaff A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG
To:
Shared Package
ML17331A665	List: ML17331A664 ML19347C922
References
NUDOCS 8103100346
Download: ML19347C922 (10)

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AVERAGE CAILY UNIT FCWER LEVEL 00CXET NO.

n_,$ :

UNIT 1

r 0 ATE 2-5-81 COMPLETED SY A. L. Tetzlaff TELEP'CNE (616) 465-5901

.TNTri January 1981 CAY AVERAGE CAILY FCWER LEVEL CAY AVERAGE CAILY FCWER LEVEL (MWE-Net)

(.Yde-Net) 1 17 1037 2

13 1052 3

19 1051 4

20 1051 5

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I)OCKET NO. 50 - 315 IINITSilllII) OWNS AND FOWER MliDilCllONS D.C. Cook - Unit 1 U NII~ N AklE DA1E Z-10-81 January, 1981 COkil'l E'IED aiY B.A. Svensson NEPORT AIONill 1El.1 PilONE (616) 465-5901 "L

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N.A.

Il 444444 Outage continued from previous month 7 Cont'd The unit was returned to service on 810105. Total length of outage 294.0 hours0 days <br />0 hours <br />0 weeks <br />0 months <br />.

Reactor power increased to 100% 810107.

170 810107 F

18.7 A

3 N.A.

HA INSTRU Unit trip due to safety injection actuation / reactor trip.

Safety in-jection was due to high differential pressure between steam leads caused by low pressure in No. 3 steam gen-erator. The initiating cause was the No. 2 main turbine stop valve drifting off its wide open position due to a faulty servo valve.

This caused the other three main stop valves to go closed resulting in a sudden increase in steam flow from No. 3 steam gen-erator thru No. 2 turbine stop valve with the resulting drop in No. 3 steam generator pressure. Unit was

' Teturned Lu :>ervice-B10108 and reached -

1 2

.i 100% power.ithe same day, 12: l'os ceil steason:

Elettinil:

linlatil G.Insaaucuimis S: Silicilnical A I apsipencos I:ailuse (1.nplain) l-klannat los Psepasanius al D.na 11 klainicnance or Test 2 Manual Suni.

Enny Slicces sin Iicen><c C Itefacting 3 Antonialac Scsans.

livens Itepins il l'lO I alc ItJilHI G-11 Hegul.itusy l(esisicelun l Ollies (Emplaint nifilI l' Opesah.s Isaining & license Ex.sminallon l' Ailininnssative 5

G Opes.stional I seus Ilimplaisil laint.it I - Same Souice l'8/11) 11 Ollies (limplaini

Docket No.:

50-315 Unit Name:

D. C. Cook Unit #1 Completed By:

D. R. Campbell Telegnone:

(616) 465-5901 Date:

February 10, 1981 Page:

1 of 2 MONTHLY OPERATING ACTIVITIES - JANUARY, 1981 Highlights:

The Unit entered the reporting period in Mode 5 in a planned outage for general maintance and inspection of the ice condensor doors.

Heatup of the Unit began January 4,1981. The Unit entered Mode 4 at 1204 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.58122e-4 months <br /> and Mode 3 at 1808 hours0.0209 days <br />0.502 hours <br />0.00299 weeks <br />6.87944e-4 months <br />. The reactor was made critical at 1622 hours0.0188 days <br />0.451 hours <br />0.00268 weeks <br />6.17171e-4 months <br />, January 5,1981 and entered Mode 1 at 1733 hours0.0201 days <br />0.481 hours <br />0.00287 weeks <br />6.594065e-4 months <br /> the same day. The reactor reached 100%

power at 0858 hours0.00993 days <br />0.238 hours <br />0.00142 weeks <br />3.26469e-4 months <br />, January 7,1981.

On January 7,1981 the Unit experienced a reactor trip with full safety injection. All ECCS systems operated as designed.

See summary for details.

The reactor was made critical at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br />, January 7, 1981.

The Unit reached 100% power at 2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br />, January 8,1981.

The Unit operated the remainder of this reporting period at 90 to 100% reactor power.

Total electrical geaeration for the month was 631,790 a:wh.

Summary:

1/7/81 At 0922 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.50821e-4 months <br />, the Unit experienced a reactor trip and safety injection.

The safety injection was actuated due to high differential pressure between steam leads, caused by a low pressure in number 3 steam generator.

The number 2 main-turbine stop valve drifted off the open position due to a faulty servo valve. The other three stop valves are slaved 7

off of the open limit switch, hence upon its drop out, these three valves went closed by means of their slow close solenoids.

There is a cross tie between the

.four steam lines upstrear of the stop valves, but the connection from each ste a lead to the cross tie is limited.in capacity by an orifice. The only stop valve thus remaining open was the number 2 stop valve, resulting in a sudden increase in steam flow in this line. As the three stop valves were closing the safety injection occurred when the differential prsssure between the steam line feedin valve (from number 13 steam generator)g number 2 stop and the other steam lines reached the 100 PSID set point, the reactor trip and safety injection was initiated.

The defective servo valve was replaced.

L

Docket No.:

50-315 Unit Name:

D. C. Cook Unit #1 Completed By:

D. R. Campbell Telephone:

(616) 465-5901 Date:

February 10, 1981 Page:

2 of 2 Summary (continued):

1/8/81 R-26 alarmed hir,h, the cause was determined to be a leaking root valve CS374 located on the VCT sample line.

The valve has been repaired and tested for leaks.

1/9/81 The East motor driven Auxiliary Feed Pump was inoperabic to repair emergency suction supply valve from the Essential Service Water system.

1/lc/81 The B.I.T. and associated 8.A.S.T. were out of Tech. Spec. when they were diluted to 19,300 PPM.

The shutdown of the Unit was started and stopped when the B.I.T. and B.A.S.T. was brought back in specification.

1/9/81 The Turbine driven Auxiliary Feedwater Pump was out of service to repair drains.

1/20/81 CD Emergency Diesel Generator was out of service

.to replace a diaphram in the starting air pilot valve.

We had rod urgent. failure alarms on three seperate occasions on 1/21/81 and 1/22/81 the cause was' loose logic cards and a blown fuse.

DOCKET NO.

50 - 315 UNIT NAME D. C. Cock - Unit No. 1 DATE 2-10-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 4 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1981 M-1 80-101-4, shell drain valve on blowdown line from No. 4 steam gen-erator had a body-to-bonnet leak and was found to be steam cut.

The valve was replaced.

_ -2 Seal water orifice flange of No. 4 RC pump leaked. Replaced gas-M kets in both flanges.

M-3 Charging line high point vent valve, CS-345, had body-to-bonnet leak.

Replaced packing cartridge and bonnet-seat assembly.

M-4 Inspected pressurizer spray valves for packing and body-bonnet leaks. Replaced bonnet gasket on NRV-164 and repacked NRV-163 and NRV-164 Valves tested satisfactorily.

M-5 Flange on loop 2 RTD header vent was leaking. Replaced flex gas-ket.

- M-6 Flange at flow orifice NFA-240 on loop 4 RTD, header return to pump suction leaked.

Replaced flex gasket.

M-7 The handholes of all four steam generators were removed and the tubes in the area of the tube lane 51ocking devices were inspected.

Some tube damage was detected in st_4m generators 1 and 4.

The affected tubes were plugged.

M-8 The containment isolation check valve on the CCW supply to the cooling coil for the main steam penetration, CCW-243-72, was leaking by. The check valve was disassembled, cleaned and re-assembled.

M-9 Pressurizer power operated relief valve. NRV-153, was leaking by.

Replaced the plug, stem, gaskets and packing. Also remachined the seats.

Valve retested satisfactorily.

M-10 Pressurizer power operated relief valves, NRV-151 and 152 were leaking by.

Gaskets and packing were replaced on NRV-151 and the plug and seats were remachined.

Reolaced the plug, stem, packing and gaskets on NRV-152 and remachined the seat.

Both valves were retested satisfactorily.

4 a

DOCKET NO.

50 - 315 UNIT NAME

0. C. Cook - Unit No. 1 DATE 2-10-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 2 of 4 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1981 M-ll Charging line motor sperated isolation valve, QMO-200, would not open.

Removed the valve operator and freed the valve.

Reinstalled the operator, replaced the motor and repaired the operator.

Reset the operator limits and tested the valve.

M-12 The 2CD2 diesel jacket water pump discharge check valve, DG-153C, would not seat. Replaced the spring and lapped the disc.

Had valve tested.

M-13 The component cooling water supply check valve to the RCP motors, CCW-122, appeared to be stuck open.

Inspected valve and lapped discs.

Reassembled valve and it functioned properly.

M-14 The West RHR pump was experiencing intermittent losses of control power.

Inspected and found a fuse clip on the main fuses loose.

Adjusted clip, cycled pump and no further ' problems were experienced.

M-15 Trip and throttle valve for the auxiliary feedpump turbine would not close.

Cleaned the contacts of the torque switch. Valve tested satisfactorily.

M-16 The cooling water line to the oil cooler for the turbine driven auxiliary feedpump had a leak at a flanged joint.

Replaced the flange gaskets.

M-17 The motor nperated ESW isolation valve to the east motor driven auxiliary feedpump, WMO-754, leaked by.

Replaced the valve and the motor on the limitorque operator.

M-18 The south :afety injection pump seal water line was leaking. Re-moved pump from service.

Replaced a nut and ferrule on swagelok fitting and returned pump to service.

M-19 The volume control tank vent regulating valve, RRV-300, had a

. packing leak.

Repacked the valve and had it tested.

M-20 The instrument line downstream of the root valve for QFI-200, charging header flow instrument, was leaking.

There was a crack in the weld where the 3/8" tubing entered a reducing bushing.

Ground out old weld, cut'off tubing and rewelded. Had the re-quired NDE performed.

DOCKET NO.

50 - 315 UNIT NAME

0. C. Cook - Unit No. 1 OATE 2-10-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 3 of 4 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1981 M-21_

The north waste gas compressor inlet valve, CCW-151N, had a bent stem.

Replaced the stem and valve bonnet.

M-22 Flange downstream of the reciprocating charging pump was leaking.

Replaced the flange gasket.

CSI-l IRV-310, the east residual heat exchanger discharge valve, failed to the open position. An air line fitting was found broken. A new fitting was installed and proper operation of the valve was verified.

C&I-2 The air hoses on NRV-151, NRV-152 and NRV-153, pressurizer power operated relief valves, were found cracked and the valve closure time was approaching the ISI time limit of 5 seconds.

The hoses were replaced with larger hoses and the closure time of the valve was reduced to less than 2.5 seconds on all valves.

C&I-3 The one inch safety valve, SV-141, downstream of FRV-275, east motor driven auxiliary feedpump emergency leak-off valve, was found leaking when FRV-257 was opened. The safety valve had been damaged due to the setpoint being too low.

The valve was repaired and the setpoint raised to 1500 psig.

C&I-4 QRV-040, No. 4 reactor coolant pump No. 1 seal leak-off valve, was closed during a surveillance test and could not be reopened.

The solenoid for QRV-040, XS0-28, located in the regeneration heat ex-changer room was removec and a spare installed. Also, the solenoid for QRV-160 and QRV-161 was replaced at this time.

Problems were previously encountered on QRV-161 solenoid. The solenoid model was HT 831654, 250 VDC.

C&I_5_.

Turbine stop valve No. 2 developed a drift problem tending to close.

The valve's servo amplifier was replaced and stop valves No.1 and No.2 were checked for proper operation.

On January 7,1981, when Unit I tripped from 100% power, the events sequence monitor indicated No. I stop valve closure was the first event in the trip.

Upon opening the stop valves on a depressurized steam header, all valves appeared to function properly.

Each valve was tested in sequence with no abnormalities.in operation observed.

'No. I stop valve showed no binding in opening or closing, nor was any drift-observed from the open position.

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

DOCKET NO.

50 - 315 UNIT NAME D. C. Cook - Unit No. 1 DATE 2-10-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 4 of 4 MAJOR SAFETY-RELATED MAINTENANCE JANUARY, 1981 C&I-5 A G. E. Company representative was called on-site for further Cont'd.

checkout of the stop valves. All limit switches were tested (with the header depressurized) and no problems were 'ound.

After Unit 1 was critical and the steam lines were pressurized, the valves were again tested. After 3 cycles, No. 2 stop valve drifted slightly closed, not enough to clear the open limit switch, but the drift was visible.

On each successive cycle, No. 2 valve drifted further closed. At the suggestion of the G. E. representative, the servo amplifier on No. 2 valve was replaced and proper operation of the valve was observed for 5 cycles, after which it was returned to service.

C&I-6 An urgent failure alarm on the rod control system Group 2 of con-trol bank D was received. The problem was traced to a blown fuse in Phase C of the moveable gripper input power supply.

The fuse was replaced with a spare.

Proper system operation was verified and the rod groups were realigned.

C&I-7 Radiation monitoring system channels R25 and R26 indicated a maxi-mum flow of approximately 9 CFM. The flow meter was replaced with a spare. The spare flow meter indicated 15 CFM. The monitor was adjusted for correct flow following the functional check of the high and low flow trips.

C&I-8 Investigate problem with monitor lights on ECCS panel being very dim. Of the two power supplies auctioneered supplying 24 vdc to the light circuits, one power supply was found tripped and could not be reset.

The second power supply output voltage was low and could not be increased through adjustment. Silicon controlled rectifiers (SCR's) were replaced in the failed power supply which restored the power supply to an-operable status. The second power supply components required replacement.

The second power supply was adjusted to provide the correct output voltage.

C&I QLS-951, primary water storage tank level transmitter, failed to the low end of scale. The temporary heat tape on the sensing line caused the water in-the sensing line to boil, resulting in-the channel failure. The heat tape was deenergized.