ML20032C475

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Monthly Operating Rept for Oct 1981
ML20032C475
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 11/03/1981
From: Nicholson W
PORTLAND GENERAL ELECTRIC CO.
To:
Shared Package
ML20032C471 List:
References
NUDOCS 8111100457
Download: ML20032C475 (7)


Text

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OPERATING DATA REPORT 30-344 DOCKET NO.

DATE 11-3-81 COMPLETED BY E O. N4aholson TELEPHONE 503/556-1713 ext. 293 OPERATING STATUS Notes Troian Nucient Plant

1. Unit Name:

' Correction to September October 1981

2. Reporting Period:

3411 hours0.0395 days <br />0.948 hours <br />0.00564 weeks <br />0.0013 months <br /> critical:

3. Licensed Thermal Power (MWt):

1216

4. Nameplate Rating (Gross MWe):

Year-to-date: 4521.8 1130

5. Design Electrient Rating (Net MWe):

Cumulative:

27283.1-1122

6. Maximum Dependable Capacity (Gross MWe):

1080

7. Maximum Dependable Capacity (Net MWe):
8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) Since IJst Report. Give Reasons:

None None

' 9. Power Level To Which Restricted lf Any (Net MWe):

NA

10. Reasons For Restrictions. If Any:

' This Month Yr. to.Date Cumulative

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74 5 (t 4-'e r hrmce) 7206 45288

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11. Hours In Reporting Period
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716.1 5237.4 27909.2

12. Number Of Hours Reactor Was Critical 0

0 2171.8

13. F.eactor Reserve Shutdown Hours 665.6 5030.6 27024.1
14. Hours Generator On-Line 0

0 1508.7

15. Unit Reserve Shutdown Hours 1864249 15962121 84528803
16. Gross Thermsl Energy Generated (MWH) 592475 5185660 27561046 j

l

17. Gross Electrical Energy Generated (MWH) 5540R4 4896432 26003191
18. Net Electrical Energy Generated (MWH) 89.3 60.0 59.7
19. Unit Service Factor 80.1 60.0 63.0
20. Unit Availability Factor 68.9 62.1 53.2
21. Unit Capacity Factor (Using MDC Net) 65 8 50.4 50.8
22. Unit Capacity Factor (Using DER Net) 10.7 6.2 22.7
23. Unit Forced Outsge Rate
24. Shutdowns Scheduled Over Next 6 Months (Type. Date,and Duration of Eschi:

None NA I

. If Shut Down At End Of Report Period, Estimated Date of Startup:

Forecast Achieved l

26. Units in Test Status (Prior io Commercial Operation):

l NA NA l

INITIAL CRITICALITY NA NA INITIAL ELECTRICITY NA NA COMMERCIA L OPER ATION 8111100457 811103 kDRADOCK 05000344 PDR (q77)

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AVERAGE DAILY UNIT POWER LEVEL l

DOCKET NO.

50-344 UNIT Troian DATE 11-3-81 COMPLETED BY k'. O. Nichol son TELEPHONE 503/556-3713.

, ext. 293 October 1981 MONTil DAY AVERAGE DAILY POWER LEVEL DAY AVER AGE DAILY POWER LEVEL (MWe Net)

(MWe Net) 1 1047 17 641 2

1050 is 6s7 3

1054 19 658 4

264 20 659 586 2]

661 6

1038 22 378 7

1050 23 6

3 1050 24 20 9

1052 25 517 10 1052 26 702 1052 27 1043-12 763 28 1053 652 29 1053 13 g4 661 30 900 j

35 666 33 435 16 668 INSTRUCTIONS On this format. list the average daily unit power levelin MWe. Net for each day in the reporting incath Compute to the nearest whole rnegswett.

(9/77) 7

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Page 1 of 3 UNIT SIIUTDOWNS AND POWER REDUCT10NS DOCKET NO.

50-344 UNIT NAME Trolan DATE 11-1-R1 COMPT.ETED fly W. O. Nicholson REPORT MONT11 October 1981 TELEPIIONE 503/556-3713.

ext. 293 i

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Cause & Corrective 8.%

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Prevent Recurrence 6

f1-16 10/4/81 F

21.5 A

3 81-025-03-L EB RELAYX Power to Preferred Instrument Bus Yll' was lost due to the failure of an output current sensing relay on inverter Y15. This affected the main feed pump speed control system, resulti ig,

in ah automatic turbine trip /readtor trip on steam generator 111-l!i 1cvel.

The relay was' replaced.

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81-17 10/12/81 F

2.8 G

3 NA.

Cil INSTRU.

The reactor tripped on low steam gen-erator level with -feed flow-steam fl<ta mismatch after an Instrument Technician performing maintenanc6 drew an arc while replacing a lead, causing a volt-age transient which affected the north main feed pump control system. This resulted in a trip of the north feed pump,and subsequent trip of the south feed pump on overspeed.

I 2

3 4-F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A Eniuipment Failure (Explain) 1-Manual for Preparation of Daia B Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee C. Refueling J-Automatic Sc.am.

Event Report (LER) File (NUREG-D Regulatory Restriction 44)ther (Explain) 0161)

E-Operator Training & IJcense Examinathm F Administrative 5

1 G-Operational Error (Explain)

Exhibit I-Same Source (9/77)

Il Other (Explain)

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DOCKET NO.

50-344 UNIT SilUTDOWNS AND POWER REDUCTIONS UNIT NAME Trnjnn DATE 11-1-81 COMPI.E1ED HY W. O. Nicholson REPORTMONTil October 1981 TELEPilONE 503/556-3713.

ext. 293

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81-18 10/22/81 F

23.5 G

3 NA EB INSTRU The reactor tripped after a Meter and Relay Technician inadvertcutly caused a bus lockout on the 12kV 111 bus supplying power to "A" and "C" reactor coolant pumps. The outage was pro-lonp,ed by high stenin generator c'nduc-o ts.Jiy caused by reverse flow through a stuckspen

  • condensate putnp. discharge check valve, flushing resin out of the full-flow demineralizers into the condensate system.

81-19 10/23/81 F

26.9 11 3

NA IIII VALVEX.

Power reduction commenced toward zero power due to a recurrence of high steam generator conductivity. At i

approximately 10% power, the reactor tripped on steam generator "D" low-low level from difficulty in manually s'

controlling level.

I 2

3 4-F: Forced Resum:

Method:

Exhibit G -Instructions S: Scheduled A.Equirmant Failure (Explain) l-Manual for Preparation of Data D. Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling J.Automalle Sc:sm.

Event Repmt (l.ER1 File (NUREG-D. Regulatory Restriction 44)ther (Explain) 0161)

E Operator Trmining & Ucense Examination.

F-Administralive 5

G. Operational Error (Explain)

Exhibit I Same Source i

(9/77)

Il Other(Explain) i

. rage 3 of 3 DOCKET NO.

' 50-M4 l'NITSilUTDOWNS AND POWER REDUCT10NS UNIT NA%f E Treinn DATE 11-3-81 COMPI.ETED ilY W. O. Nichelsop REPORT MONTil _0c tober 1981 1ELEPil0NE 503/556-3713, ext. 293 s

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81-20 10/30/81 F

4.7 A

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. INSTRif The react.or tripped on low steam i

generator 1evel with feed flow-steam

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I flow mism. itch after "D" feed reg.

valve went shiit.

The valve shut due to.a burned out air. vent solenoid coil for feedwater isolation which was-replaced.

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4-F: Forced Reason:

Methml:

Exhibit G. Instructions S: Scheduled A Eetuipment Failure (Explain) 1-Manual for Preparation of Data B. Maintenance of Test 2-Manual Scram.

Entry Sheets for Licensee 1

C Refueling 3 Automatic Sc.am.

Event Report (LE R) File (NUREG.

D-Regulatory Restriction 4 Other(Explain) 0161)

E-Operator Training A License Exondnathm F Administsative 5

G Operational Errua(Explain)

Exhibit i.Same Source (9/77) 11-01her (Explain) t

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DOCKET No: 50-344 DATE:

11-3-81 COMPLETED BY:

W. O. Nicholson TELEPHONE:

503/556-3713, ext. 293 SU'04ARY OF OPERATINC EXPERIENCE OPERAI!2N:

The plant entered the month of October operating at 100% powe.

On October 4, the reactor tripped due to a burned out relay in the static inverter on Preferred Instrument Bus Yll.

Two air leaks inside Containment were repaired before retur71ng the plant to service 21 hours2.430556e-4 days <br />0.00583 hours <br />3.472222e-5 weeks <br />7.9905e-6 months <br /> later.

An Instrument Technician performinb maintenance drew an-arc while replacing a lead, resulting in a voltage transient which caused a reactor trip on October 12.

The plant was returned to power within three hours. The north condensate pump fciled during the trip, limiting plant power output to 65%

until the pump was repaired and returned to service on October 26.

Two damaged bowls were replaced on the pump and a complete inspection was per-formed on the moter.

On October 22, the reactor tripped when a Meter and Relay Technician caused a bus lockout on the 12kV bus supplying power to "A" and "C" reactor coolant pumps.

The outage was prolonged by high steam generator conductivity caused by reverse flow through a stuck-open condensate pump discharge check valve flushing resin out of the full-flow demineralizers into the condensate system.

Thg plant was returned to service af ter 23 hours2.662037e-4 days <br />0.00639 hours <br />3.80291e-5 weeks <br />8.7515e-6 months <br />.

The plant was taken of f the line on October 23 due to a recurrence of 1.igh steam generator conductivity during power excalation.

Conductivity was reduced to within specification and the plant returned to ser. ice 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> later.

On Octobef 30, the reactor tripped when the "D" feed regulating valve shut.

A burned out air vent solenoid coil for feedwater isolation was replaced ano the nlant returned to service within five hours. Power was 'oeing increased toward 100% as the month ended.

The Reactor Coolant System gross gamma activity increased f rom approximately 10pCi/ml to about 23uci/ml before decreasing to 17vCi/ml at the end of the month. Activity had not completely stabilized due to plant transients.

Radiochemistry analysis show.c suspected fuel failure in 10 to 15 rods in the once-burned fuel region "E."

MAJOR SAFETY-REIJTED MAINTENANCE:

Air leaks were repaired on the "B" reactor coolant pump standpipe fill and seal return valves.

Annual preventative maintenance was completed on the diesel-driven fire pump.

Hanger work was completed on the east Emergency Diesel Generator exhaust pipe.

~

1

SUMMARY

Oi OPERATING EXPERIENCE (Contd.)

MISCELLANEOUS MAINTENANCE:

l Two damaged bowls were replaced on the north condensate pump.

Electric auxiliary feed pump functional test was compieteu satisf actorily.

Continued work outside containment on the Reactor Vessel Level Indicating.

System-(RVLIS).

i Completed annual inspection on the east Turbine Building Cooling Water -

Pump.

A gas leak was repaired on the West Waste Gas Compressor.

Continued work on the post-accident sampling system.

Replaced air vent solenoid coils for feedwater isolation on "C" and "D" feed regulating valves.

LICENSE CHANGES:

4 None.

MISCELLANEOUS:

Work continued throughout the month on the Technical Support Center with the fire main initial pressurization test completed and the 12kV power supply installed.

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