ML20066D994
| ML20066D994 | |
| Person / Time | |
|---|---|
| Site: | Cook  |
| Issue date: | 11/04/1981 |
| From: | Might A INDIANA MICHIGAN POWER CO. (FORMERLY INDIANA & MICHIG |
| To: | |
| Shared Package | |
| ML20066D987 | List: |
| References | |
| NUDOCS 8211120373 | |
| Download: ML20066D994 (11) | |
Text
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,,, CPERAT:NC DATA RI?CRT DCC:GT NO.
5d-316 DATI 11-4 Al CO.NL*LETED EY A. Miaht TILE?SCyg __616-4M -6901 CPERATING S-ATUS N8 Donald C. Cook Plant 2
- 1. Unir N=me.
October 1981
- 2. Reportiss ?sdod:
3391
- 3. t '--M The:= 1 ? owe (MW:):
1133
- 4. N2=colate R.:d=;(Csoss 51W ): _
1100
- 5. Design I!e==i=1 R::ia:(Nec 31We):
1118
- 6. 5f-" sun: Depend:hte Capci:y (Cross 51We):
I082
- 7. Sime ---n Deped:hl C:p:ci:7 (Net 31We):
- 3. If C.:n;es Oc=ar in Capaci.y Rathgs (It==s Number 3 Th:oegh 7) Sine: L:s: Report. Give R:: sons:
- 9. Power L: vel To Which Res:==ed. !! Any (Net MWe):
- 10. Resons For R_s=i does.lf Asy:
This Month Yr.-<o.Dacs Cc==I:dve 745 7,296 33,600
- 11. Hot s != Repords; P: dad 103.3 4,815.9.
22.561
- 12. Nu=h=r of Hoc:s R==:or Wss C&f=1 0
0 0
- 13. Recor Rese. e Shn:down Ec==
9/ 6 4.717.4 21.757
- 14. Hours Ce===:ce ca.Lh, 0
0 0
- 15. U:!r R. serve Shutdown Hot =s 284,784 15.487,474 69,107,108
- 16. Cross Thm ! E==rgy Cene=ted (3tWM)
- 17. Cross E!e==i=f Ise y Ce==:::md G.tWH) 89,630_
4,993,160 22,084,980
- 13. Net Ele==i=1 I:::;y Ce===:_s C. WE) 85,946 4,817,860 21,277,025 13.1 64.7-69.9
- 19. Unit serri==.:se:ar 13.1 64./
69.9 2C. Unit Ar.il:biE:7 :c:or F
10.1 61.0 65.0
- !. Unit C:pci:7 :c:er(Us!== MDC Nee) 7 10.5 60.0 64.3
- 22. Unit Capscity F:=or(Using DER Net) 86.9 13.4 15.0
- 23. Unir. ore:d cu::ge Rate
- 24. Shutdowns Scheduled Over Nex: 5 Man:hs< Type. D:te.: d De= don of E:ch1:
- 25. !! Sh:: Dowr At Isd Of Report ?:-iod. I:ti==:ed D:ce of Scar: p:
. 25. Units Is Tes: S=:us (P:for to Ce====i21 Open: ion):
Fore =st Achieved INITIAL CRIT *CALITY
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INITIAL E1.ICTR:C;W CO i?.iERCIA: OPERA 7 ON PriTI 8211120373 821112 PDR ADOCK 05000315 R
r AVERAGE DAILY UNIT POWER LEVEL
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DOCKET NO.
50-316 UNIT 2
DATE 11-4-81 COMPLETED BY A. Might TELEPHONE 616-465-5901 MONTH October 1981 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWE-Net)
(MWe-Net) 1 1065 17 2
534 18 '
3 19 4
20 5
21
~~~-
6 22
--~~
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7 23
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310 8
24 11 9
25 10 25 11 27 12 28 13 29 14 30,
609 15 31 1052 16 NSTRUCTIONE n this format list the average daily unit power level in MWe-Net for each oay in the raporting month. Ccmoiste to the nearest whole megawatt.
m UNITSiluTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-316 UNIT NAnlE _D.C. Cook - Unit 2 DATE 11-12-81 October, 1981 COMPLETED HY B.A. Svensscn REPORT AIONTil TELEPIIONE (616) 465-5901 PAGE 1 of 2 "t.
u e
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Yf Licensee
[ s,,
D, Cause & Cinreceive No.
Date g
3g
, y cd Event y
g{
Action to g3 5 cE j ifi g Report #
mO 8-Psevent Recurrence c5 102 811002 F
525.7 A&B 1
N.A.
CC HTEXCH Unit removed from service due to in-crease in primary to secondary leakage through Steam Generator No. 21. Max-imum measured leak rate was 0.292 gpm.
Hydrostatic testing' revealed leakage from tubes 78 and 79 in Row 1 on the cold leg side.
Eddy current testing showed a defect in tube 74 in the same row. All three tubes were plugged.
Outage was extended to permit com-pletion of NUREG-0737 required design changes and other maintenance work.
The unit was returned to service on 811024.
103 811025 F
1 21.7 A
1 N.A.
CB VESSEL Power ascension from the previous out-age was stopped at 78% due to indica-tio.n of primary leakage based on ab-normally high readings on the contain-ment atmosphere particulate radio-activity monitor.
/ Continued.....
I 2
3 4
F: Foicett Reason:
klethoti:
Eniiihis G. Insienctions S: Scheilulcil A.Eiguipment Failme(Explain) 1-Manual for Preparation of Data h.klainienance or Test
- 2. Manual Scram.
Ent y Slicess fus 1.icensee C-Refueling 3 Autenuatic Scram.
Evens Repose (1.ER) File INURIG D.Regulainiy Restricitun 4-Other (Explain) 0161)
E-Operator l' raining & License lixamination F Atiministrative 5
G-Operational Esior IExplain)
' Exhibit 1 - Same Somce 19/77)
Il Olher (Explaini i
.- m DOCKET NO. 50-316 UNITSilUTDOWNS AND POWER REDUCTIONS UNIT N AhlE D.C. Cook - Unit 2 DATE 11-12-81 October,1981 COhlPl.ETED HY B.A. Svensson REPORT AIONTil TEl.EPHONE (616) 465-5901 PAGE 2 of 2
,5, E 3
Y 1.lcensee
,E-t, Cause & Causeelive o
No.
Dale
.g Eg 5
jg5 Event g'g gU'8 Action to j;f3g itepine #
mO Prevent Hecussence H
g 6
(103 The unit was removed from service.
Continued)
The suspected leak was discovered to be at the gasket joint on the pres-surizer manway.
Following repairs the unit was returned to service on 811030.
100% reactor power was reached at 2245 hours0.026 days <br />0.624 hours <br />0.00371 weeks <br />8.542225e-4 months <br /> the same day.
I 2
3 4
F: Fusced Iteason:
klethod:
limhible G Instinctions S: Scheduled A l?quipmens l'ailure(Explain) l klanual for Picparation of D. iia ll klaintenance of Test 2 Manual Scram.
linary Sheets for 1.icensee C Refueling 3 Automatic Scram.
Evens Repin II.l!R) FileINURI:G-D.Hegulatiny Restriction
-l-Other (Explain) 0161)
E Operator Isaining & l.icense lixamination F Administiative 5
G Operational liiso Ilixplain)
'lixhibil 1 - Same Somce 19/77)
Il Other (Explain) 6
Docket No.:
50-316 Unit Name:
D. C. Cook Unit #2 Completed By:
C. E. Murphy Telephone:
(616)465-5901 Date: November.4, 1981 Page:
1 of 2,
MONTHLY OPERATING ACTIVITIES - OCTOBER,1981 Highlights:
The Unit entered this reporting period operating at 100% power.
At 0449 on Friday, October 2, the Steam Jet Air Ejector Monitor (R-15) alanned, indicating an increase in the primary to secondary leakage in the #21 Steam Generator. The Unit was removed from service at 1352 on Friday, October 2 and was cooled down to Mode 5 by 0205 on Saturday, October 3.
Two leaking tubes and one possible " leaker" on the affected Steam Generator were plugged.
During this Unit outage, a considerable amount of time was expended while the Reactor Coolant System was heated up and cooled down to allow for the proper positioning of the four Steam Generator Shim packs and to repair various other miscel-laneous leaks.
At 0805, Saturday, October 24, the Reactor was made critical and the turbine / generator was paralleled at 1137.
The Reactor power level was increased to 78% by 2208, Saturday.
During this power increase the reading on the Containment APD Monitor (R-11) increased significantly, ir.dicating a RCS leak in the Containment.
The leak was discovered to be on the Pressurizer Manway Gasket.
Cooldown and degassing was begun and the Unit was placed in Mode 5 at 1022 on Monday, October 26.
The Pressurizer Manway leak was repaired on Wednesday afternoon, October 28 and the Unit heat-up began at 0630, October 29.
The Reactor was made Critical at 0123 on Friday, October 30 and the Turbine / Generator paralleled at 0307.
100% power was reached at 2243 on Friday and has been maintained at that level since that time.
Total electrical generation for this month was 89,630 mwh.
Summary:
10-1-81 The East Centrifugal Charging Pump was inoperable for a 3.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for Maintenance to repair the out-board Mechanical Seal Heat-Exchanger.
~10-7-81 "AB" Emergency Diesel was out of service for a 34.5 hour5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> period for Maintenance to inspect the Starting Air Valves.
10-20-81 At 1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />, an inadvertant S.I. signal was initiated on " Train B" only. All Safety Equipment responded as it should. The S.I. was due to C & I Technician in the S.S.P.S. cabinet performing a surveillance.
Docket No.:
50-316 Unit Name:
D. C. Cook Unit #2 Completed By:
C. E. Murphy Telephone:
(616)465-5901 Date: November 4,1981-Page: 2 of 2 10-21-81 At 1106 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.20833e-4 months <br />, the No. 21 Circulating Water pump tripped.
Cause of the trip was discovered to be a small fire in the motor windings, which was quickly extinguished. The damaged motor was replaced with a spare.
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DOCKET NO.
50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 11-12-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 1 of 5 MAJOR SAFETY-RELATED MAINTENALCE OCTOBER, 1981 M-1 No. 3 boric acid transfer pump was leaking.
Replaced the mechanical seal and shaft bearing oil seal deflector.
Had pump tested.
M-2 No.1 steam generator pressure instrument root valve, MPI-212V1 had a body-to-bonnet leak.
M-3 Component cooling water valve, CCW-135 was leaking by.
Disassembled,
cleaned internals and reassembled valve.
M-4 RCS loop 2 RTD loop isolation valve, RC-106L2 had a body-to-bonnet leak.
Replaced all 12 bonnet studs and the bonnet gasket.
M-5 RCS loop 4 RTD loop isolation valve, RC-107L4 had a body-to-bonnet leak.
Replaced 5 bonnet studs and the bonnet gasket.
M-6 Pressurizer safety valve, SV-45C was leaking by.
Tested a spare valve and installed it in place of the valve that was leaking.
M-7 Boric acid transfer system isolation valves, CS-418-S and CS-422S were leaking by.
Replaced the valve diaphragms.
M-8 No. 2-1, steam generator had primary to secondary leakage.
Inspected visually and located two leaking tubes.
Eddy current testing identified a defect in a third tube.
Plugged all three of the row 1 tubes.
M-9 Pressurizer power operated relief valve, NRV-152 was leaking by.
Dis-assembled valve and inspected.
Reassembled using new seat, seat ring, plug and gaskets.
Reassembled and repacked valve and had it tested.
M-10 Pressurizer power operated relief valve, NRV-153 was leaking by. Dis-assembled valve and inspected.
Reassembled using new plug, seat ring and gaskets. Had valve. tested.
M-ll The normal charging line check valve to loop 4, CS-329L4 had a body-to-bonnet leak.
Repaired the body-to-bonnet leak and replaced the bonnet studs.
M-12 No.1-steam generator stop valve dump valve, MRV-211 was leaking by. '
Machined the plug and seat ring and had valve tested.
M-13 The emergency boration flush valve, PW-265 was leaking.
Replaced the diaphragm.
DOCKET N0.
50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 11-12-81 COMPLETED BY B. A. Svensson
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TELEPHONE (616) 465-5901 PAGE 2 of 5 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1981 M-14 The pressurizer spray control valve, NRV-163 was leaking.
Replaced the bonnet and cage gaskets and one stud.
Had valve tested.
M-15 The sample isolation valve for No. 21 steam generator, DCR-301 was leaking by.
Replaced the sample valve and tubing.
Had necessary NDE performed and had valve tested.
M-16 Attachment weld for the east RHR heat exchanger safety valve, SV-104E broke.
Removed flange and pipe nipple and installed new. Had necessary NDE performed and completed hydrostatic test.
M-17 An internal inspection of safety injection system check valve, SI-152S revealed that the valve disc and disc hanger were not installed.
In-stalled a new disc and disc hanger.
1 M-18 Attachment weld for the west RHR heat exchanger safety valve, SV-104W broke.
Removed flange and pipe nipple and installed new. Had necessary NDE performed and completed hydrostatic test.
M-19 Letdown heat exchanger, SV-51 was leaking by.
Verified setpoint of spare safety valve and replaced SV-51.
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M-20 Blowdown sample isolation valve, BD-102-4 was leaking.
Replaced the bonnet gasket, repacked the valve and replaced one packing gland stud.
M-21 Loop 4 RCS RTD loop isolation valve, RC-103L4 had a packing leak.
Re-packed the valve.
M-22 The pressurizer manway was leaking.
Replaced manway gasket and two bolts which were steam cut.
Leak test was performed.
M-23 The west centrifugal charging pump seal water supply valve, QM0-226 had a packing leak.
Repacked valve and had it tested.
M-24 Reactor coolant loop 1 RTD bypass loop valve, RC-108-L1 failed.
The valve disc was separated from the stem., Replaced valve and had NDE performed as required.
Performed system leak test.
M-25 Letdow'n orifice regulating valve, QRV-162 had an operator diaphragm air leak.
Replaced diaphragm, repaired valve bonnet leak and had valve tested.
DOCKET N0.
50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 11-12-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-590T
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PAGE 3 of 5 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1981 C&I-l DCR-340 when cycled required greater than 10 seconds to close. The valve was inspected and the problem identified as the packing being too tight.
The packing was loosened and a retest of the valve's cycle time was performed.
The measured closure time was recorded as 8.0 seconds.
C&I-2 2PB-936AB, Containment Pressure Protection Set II indicated signs of drift during surveillance testing.
The bistable was removed and a spare was installed.
Following calibration of the bistable, the trip set-i point was monitored for a one-week period to ensure proper operation.
C&I-3 Circuit 71 of the Containment Fire Detection System actuated the trouble alarm on the CAS. The thermistor string terminator required replacement.
The trouble alarm cleared.
C&I-4 The rod bottom light for control rod D4 did not illuminate with the con-trol rod at less than 20 steps. The rod bottom bistable and signal con-ditioning modules were recalibrated and returned to service.
C&I-5 The red pen of MR-50, Containment Dew Point Monitor failed to the high end of scale. The detector mirror was cleaned.
The system failed to balance with the mirror cleaned and the detector was replaced.
During the balancing of the red pen channel, the blue pen channel's sample Jump was noticed overheating. The sample pump was examined and the fan 3 earings were found to be galled.
The pump was replaced with a spare.
Normal operation of both channels was verified.
C&I-6 NTP-241, Delta T-Tavg Protection Set IV cold leg normal RTD failed to an open circuit condition.
The failed RTD was removed and a spare RTD was installed and spliced to the cable.
C&I-7 NFA-210, Reactor Coolant Loop No.1 RTD bypass manifold return flow alarm, low flow alarm was actuated with 325 gpm flow present. The zero of the instrument had shifted.
The zero was adjusted and the cal-ibration test points were within specifications. The alarm microswitch required replacement.
The setpoint was adjusted to actuate at 283 gpm decreasing.
C&I-8 The boron injection tank train A heater would not fun'ction properly.
The bistable utilized for heater control was found failed.
The bi-stable was replaced and the installed spare bistable was calibrated to energize the heaters at 160 F decreasing and deenergize the heaters at 1700F increasing.
The entire temperature loop was tested to ensure re-liability of the control system.
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l DOCKET N0.
50 - 316 UNIT NAME D. C. Cook - Unit No.
DATE 11-12-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-590T PAGE 4 of 5 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1981 C&I-9 On August 10, 1981, the Lower Containment Sump Level Channels NLA-310 and NLI-311 displayed a large deviation between channels.
During the outage, the low side bellows was determined to be the cause of the problem through a static pressure test.
The bellows and sensing line were replaced and the oil fill of the bellows and sensing line was accomplished with the assistance of a Barton Company Field Representa-tive.
The channel was calibrated and returned to service.
C&I-10 The Loop 1 Delta T-Tavg Protection Set Power Level indicated at test point TP-412J, was below the other loops. The calibration of the re-sistance to voltage converters was tested and TY-411A was found to be out of specifications. TY-411A was recalibrated and returned to normal service.
C&I-ll BLP-140, Steam Generator No. 4 narrow range protection set indicated a level 16% higher than the adjacent protection channels. The trans-mitter was isolated and the reference leg was blown down.
The trans-mitter was valved in and correct indication was observed on the channel.
C&I-12 On September 8,1981, the Flux Mapping System Detector Position Switch for Detector F failed to register the correct detector position.
During movement, the detector failed to stop at the bottom of core and top of core positions.
Initial investigation indicated a problem with the de-tector drive encoder.
The position encoder, power supply and several nixie display tubes were replaced. The detector channel position en-coder was adjusted for the correct detector position and the system was returned to normal.
C&I-13 The AB Emergency Diesel Temperature Recorder indicated the rear No. 5 and front No. 4 thermocouples higher than normal.
The temperature in-dication for No. 5 rear was tested and determined to be indicating properly.
The thermocouple for No. 4 front was testeg and was replaced.
The new thermocouple's indication returned to the 119 value.
C&I-14 ECR-31, Containment Isolation Valve for Radiation Monitoring System Channels R-11 and R-12 would not open completely.
The problem was traced to solenoid valve, XS0-631 which was found in an intermediate position.
The solenoid valve was disassembled and rebuilt.
The re-built solenoid and valve were functionally tested with the measured cycle times of 1.4 seconds opening and 2.7 seconds closing.
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DOCKET NO.
50 - 316 UNIT NAME D. C. Cook - Unit No. 2 DATE 11-12-81 COMPLETED BY B. A. Svensson TELEPHONE (616) 465-5901 PAGE 5 of 5 MAJOR SAFETY-RELATED MAINTENANCE OCTOBER, 1981 C&I-15 The Rod Position Indication System Panel Meters all indicated a po-sition of 25 steps with all rods on bottom. The low voltage RPI power supplies PS-2 and PS-4, supplying -13 VDC to the signal conditioning i
modules operational amplifiers were found defective. The supplies were replaced and the panel indicators returned to their previous zero readings.
C&I-16 Pressurizer Spray Valve NRV-163, would drift open while the controller was indicating e closed condition. The valve's positioner was found to have a worn pilot valve stem which was allowing air leakage. The pilot stem was replaced and correct operation of the valve was verified.
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