ML20138R622

Monthly Operating Rept for Aug 1985

ML20138R622
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	08/31/1985
From:	Orser W, Ulmer F PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
WSO-563-85, NUDOCS 8511180702
Download: ML20138R622 (6)

Text

.

OPERATLNG DATA REPORT

' DOCKET NO. 50-344 DATE

, COS!PLETED BY F. J. Ulmer l TELEPHONE s01 ssr,-3713 l Ext. 495 OPERATING STATUS l

Notes

1. Unit Name: Troian Nuclear Plant August 1985 l 2. Reporting Period:

3411

3. Licensed Thermal Power (MWt): 2 6

4. Nameplate Rating (Gross MWe):

1130 l 5. Design Electrical Rating (Net MWeJ:

1122

6. Slaximum Dependable Capacity (Gross MWe):

1080 7.. Maximum Dependable Capacity (Net MWe):

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since Last Report. Give Reasons:

N/A "I^

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

10. Reasons For Restrictions. If Any: N/A This Month Yr. to-Date Cumulative 1

744. 5,831. . 78,887.

11. Hours !n Reporting Period 46,785.5 735.24 4,039.8

12. Number Of flouri Reactor Was Critical 0.0 3,887.4 0.0

13. Reactor Reserve Shutdown Hours 3,958.9 46,294.4 733.8

14. hairs Generator On Line 0.0 0.0 3.249

15. Unit Reserve Shutdown Hours 2.491.756. 13.168.477. 146.138.226

16. Gross Thermal Energy Generated (MWH) 804,782. _, 4,222.716 47.778,516

17. Gross Electrical Energy Generated (MWH) 768,835. 4,013,062. 45,163,592.

18. Net Electrical Energy Generated (MWH) 8 7 98*6 D7 9 j 19. Unit Service Factor 62.8 98.6 67.9

20. Unit Availability Factor 95.7 61.7 51.0

21. Unit Capacity Factor (Using MDC Net) 9I 4 60 9 50.7

22. Unit Capacity FactorIUsing DER Net)

23. Unit Forced Outage Rate 14 7I 16.4

24. Shutdowns Scheduled Over Next 6 \tonths (Type. Date,and Duration of Each :

M/A

25. If S:iut Down At End Of Report Period. Estimated Date of Startup: N/A

26. Units in Test Status (Prior io Commercial Operationi: Forecast Achieved i J

" ^ "I^

INITIA L CRITICALITY N/^ N/^

INITIA L ELECTRICITY COMMERCIAL OPER ATION M/A M/A I

I 0511100702 050031 - [ O (- (0/77)

PDR ADoCK 05000344 l R Pon  ; l J

i

, AVEI; AGE DAILY UNIT POWER LEVEL i

DOCKET NO: 50-344 UNIT: Trnjnn DATE:_

i COMPLETED BY: F. J. Ulmer J TELEPHONE: (503) 556-3713 Ext. 495 MONTH August 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net)

! 1 1060 17 1044

! 2 1051 18 1054 1 3 1055 19 1058 4 1060 20 1058 5 1060 21 1057 6 1059 22 1050 7 1062 23 1039 8 1058 24 1044 9

1062 25 1048 I

I 10 1056 26 527 11 1055 27 965 12 1052 1058 28 i

1044 1055 13 29 1948 1059 14 30 1050 1059 j 15 31 1

039

~

16 1.

j INSTRUCTIONS i On this format, list the averago daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

UNIT SifUlDOWNS AND POWER REDUCTIONS DOCKET NO. 50-344 UNIT N AME Trolan DATE REPORT MONill Auqust COMPLElED HY F_ 3_ Ti1mor 1ELEPHONE (5011 sqr. 7713 Ext 495 W. Date g-

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5 hIk 2g&

Licensec Event

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9.s Cause A Currective Action so fE E jgg Repost

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]O Prevent Recurrence 6

85-06 850826 F 10.2 G 3 85-10 ED TRANSF Reactor trip due to multiple 2-ou :: -

of-4 SSPS trip logics being met.  ;

Simultaneous to the performing of a-periodic instrumentation and cont ol  !

test (PICP) on Reactor Protection Set I IV, an i."strument and control tec 1-nician accidently shorted a heat trace circuit to an au::iliary fee 1-water flow instrumentation device which lowered the voltage on 120 rac l preferred instrument bus Y13 suff L- i

) cently to cause the bistables on  !

Reactor Protection Set III to act late thus causing a reactor trip. The l shorted heat trace circuit was i l

corrected. Trojan is reviewing t le adequacy of the preferred instrumont l power supply inverters.

i I 2 3 4 F: Torced Reastm: Method: Exhibit G - Inst ructions 5: Scheduled A-Equipment Falluee(Explain) I-Manual for Preparation of Data 84taintenance of Test 2-Manual Scram. Entry Sheets for Licensee ,

C. Refueling 3- Automatic Sc.am. Event ReputI(LER) Fife (NUREG-D Regulatory Restrictitm 4 0ther (Emplain) 0161)

T Operator Training A Ucense Esamination T-Adnunistratise 5 G Ore'J8ional E8'ag IEuplain) .

Exhibit I . Same Source

, ptf77) Il othes (Esplain t l

I

SUMMARY

OF OPERATING EXPERIENCE DOCKET NO: 50-344 DATE:

COMPLETED BY: F. J . Ulmer TELEPHONE: 503-556-3713 OPERATION:

SEE ATTACHED MAJOR SAFETY-RELATED MAINTENANCE:

1. Train A ESF equipment outage for scheduled routine maintenance.

2. Train B ESP equipment outage for scheduled routine maintenance.

3. Roset reactor low pressure trip, reactor safety injection low pressure trip setpoint, and pressurizer high level trip setpoint to 1890, 1855, and 88% respectively. Readjusted control pressure of RCS to 2255 psig indication.

MISCELLANEOUS MAINTENANCE:

1. Repaired containment condensate return valve (No-1605)

2. Auxiliary feedwater pump recirculation line leak repaired.

3. Replaced valve manifold for FIS-3004A2 auxiliary feedwater flow.

4. Replaced speed switch on H Emergency Diesel Generator.

LICENSE CHANGES:

tiotlE ,

MISCEL*ANEOUS:

tiotlE

Operation:

The plant entered the month of August in Mode 1 at 100% power. Except for the turbine control valve testing on 2, 16, and 29 of August, no major power reductions occurred with the exception of the August 26 plant trip. Due to warm summer weather, slight decreases in turbine load were necessary due to high condenser back-prossure. The warm weather caused higher transformer temperatures on August 16 and main transformer spray cooling was initiated to maintain full power j operation.

On August 21, the low pressure reactor trip setpoint was changed from 1865 to 1890 psig. The change resulted from inaccuracies in

the instrument calibration from not including in the calculations

) the hydrostatic head of water above the instrument. On August 28, i the low pressure safety injection setpoint (1835 psig) and the pressurizer high level trip setpoint (92%) were changed to 1855 psig ,

and 88% respectively. The SI setpoint change was due to inaccuratos j in instrument calibration as stated above and the pressurizer high

! lovel trip setpoint was changed as a result of transmitter drift.

The control setpoint for RCS pressure was increased by 20 psig.

At 1155 on August 26, the reactor automatically tripped from full load. The reactor trip was caused by an instrument and control tech-nician accidently shorting a heat trace circuit on the flow instrument (FI-3043C2) while Reactor Protection Set IV was tripped for routino

! testing (PICT-ll-1). The short caused a voltage dip on proforred 120 vac bus Y13 which supplies Reactor Protection Set III. The

] voltage dip caused several bistables to actuato in Protection Set l III, thus completing 2-out-of-4 trip logic for multiple reactor trips i in coincidence with Protection Set IV. The trip wac immediately 4

i identified and correctivo action taken to correct the heat traco circuit. The Trojan staff is presently re-ovaluating the adoquacy of proferred instrument power supplies.

At 2041 on August 26, the reactor was taken critical. At 2107, a i turbine trip occurred during turbine roll testing from steam gonorator +

C water level swell which occurred when turbino control valvo CV-2 came off its closed sont position. This trip caused a foedwater i isolation signal, main food pump trip, and auxiliary foodwater nystem  ;

) automatic actuation. Steam gonorator levels woro returnod to normal 1 and the main turbino was synchronized to the grid at 2207. The plant 1

continued through the month at full power without incident.

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Portland General Electric Compan)

Trojan Nuclear Plant P.O. Bos 439 Rainier, Oregon 9704S (503)556-3713 September 5, 1985 WSO-563-85 Office of Resource Management US Nuclear Regulatory Commission Washington DC 20555 Gentlemen:

In accordance with the Trojan Nuclear Plant Technical Specifications reporting requirements, the monthly report is submitted for August, 1985.

Sincorol-W. S. Orsor General Manager WSO/GbBapat Attachment c: Distribution File 93.24b

' I

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