ML20135B599

Monthly Operating Rept for June 1985

ML20135B599
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/30/1985
From:	Orser W, Peterson L PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
WSO-443-85, NUDOCS 8509110112
Download: ML20135B599 (6)

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OPERATING DATA REPORT DOCKET NO. 50-344 DATE 7-1-85 COstPLETED BY L. S. Peterson TELEPHONE Isnais;6-3713 Ext. 496 OPERATING STATUS Notes Trojan Nuclear Plant

1. Unit Name:

June, 1985

2. Reporting Period:

34I1

3. Licensed Thermal Power (51Wt):

1216

4. Nameolate Rating (Gross 31We):

1130

5. Design Electrical Rating (Net stWe):

1177

6. Siaximum Dependable Capacity (Gross 51We1:

7. Staximum Dependable Capacity (Net 5tWe):

1080

8. If Changes Occur in Capacity Ratings (!tems Number 3 Through 7) Since f.ast Report. Give Ressons:

N/A

9. Power Level To Which Restricted.lf Any (Net StWe): N/A

10. Reasons For Restrictions.lf Any: M/^ .

This 5tonth Yrao.Date Cumulative 720. 4.343. 77 190

11. Hours in Reporting Period 0.0 2.767_4 4s s11 1

12. Number of Hours Reactor Was Critical 0.0 0.0 3.887.4

13. Reactor Reserve Shutdown Hours 0.0 2.749.5 45.085.0

14. Hours Generator on-Line 0.0 0.0 3.249.0

15. Unit Resette Shutdown Hours

16. Gross Thermal Energy Generated (51WH) 0.0 9.202 17a. 141 1nn san

17. Gross Electrical Energy Generated (5tWH) 0.O _,

2.942.494. 46.498.274_

-3.854. 2.799.254. 41.049_7n4

18. Net Electrical Energy Generated (5tWH)

O.0 63.3 58.2

19. Unit Service Factor 62.4 0.0 63.3

20. Unit Availability Factor 0.0 59 7 52_6

21. Unit Capacity Factor (Using SIDC Net) 0.0 57.0 50.2

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outsge Rate 0.0 6.0 16.6

24. Shutdowns Scheduled Over Next 6 Stonths(Type.Date.snd Durstion of Eachl:

25. If Shut Down At End Of Report Period. Estimated Date of Startup: Julv 6 fans

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY n/n n /n n/n n/n INITIA L ELECTRICITY n/a n/a C05talERCIAL OPER ATION 8509110112 850630344

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s Summary of Operating Experience Operation:

The plant entered the month in mode 6. After completion of the inser-vice inspection of the reactor vessel, the lower internals were installed. Core reloading began at 1743 on June 4th and was completed on June 9th. After installation of the upper internals and reactor vessel head, the plant entered mode 5 at 1525 on June 17th. A bubble was drawn in the pressurizer on June 25th and cold control rod drop testing completed on June 26th.

An inadvertent safety injection (SI) occurred on June 30th during Instrumentation and Control (I&C) testing of the reactor protection system. The plant was in mode 5 at the time with RCS pressure at 350 psig. During testing of the reactor trip breakers, the low pressur-izer pressure safety injection signal was inadvertently unblocked by simulating a high pressurizer pressure signal. Upon completion of the testing the elevated signals were removed and a SI actuation oc-curred due to the actual low pressurizer pressure conditions.

After recovering from the SI the plant entered mode 4 at 1830 on June 30 in preparation for a return to power operation.

Major Safety-Related Maintenance:

Performed eddy-current inspection of 100% of the tubes in the 'B' and

'C' steam generators. Three (3) tubes in the 'C' generator were plugged.

Completed the 10-year reactor vessel inservice inspection. No record-able indications were found.

Refurbished all safety-related hydraulic snubbers.

Completed mechanical snubbers inspection and replaced units which failed to meet test acceptance criteria.

Completed local leak rate testing of containment isolation valves.

Modified controls for the turbine driven auxiliary foodwater pump to allow an immedate restart of the pump from the control room.

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Continued modifications to environmentally qualify equipment located in the main steam support structure.

Modified circuitry for valves supplying component cooling water to the' reactor coolant pumps such that the valves close on a phase 'B' Containment Isolation Signal (on !!i-Ili containment pressure or manual containment spray actuation) instead of a phase 'A' containment isola-tion signal (any safety injection signal or manual containment isolation signal).

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Miscellaneous Maintenance:

Complete inspection and refurbishment of the high pressure section of the main turbine.

Replaced the three number 1/2 feedwater heater tube bundles in A train feedwater system. Also replaced the four number 3 and 4 feedwater heat exchangers in both trains.

Repaired the rotor on the 'A' main feedwater pump turbine.

Modified the main feedwater pump recirculation system to allow for gradual opening of the control valve to eliminate stop changes in flow rate when the valve actuates.

Performed ultrasonic thickness measurements on steam and high energy fluid piping in the secondary plant. Replaced piping that showed thin-ning.

Completed sludge lancing of the steam generators.

License Changes:

None Miscellaneous:

During eddy current inspection of the 'B' steam generator, three foreign objects were noted on the primary side of the generator. The objects were determined to be a small piece of wire, a piece of debris from the lower internals hole cutting operations (which took place during the upflow modification in the 1984 refueling outage), and a fastener-type device of non-RCS origin. This debris was all removed from the steam generator following level instrument accuracy enhancements.

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+ AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-34 4 UNIT: Troj an DATE: 7-1-85 COMPLETED BY: L. S. Potorson TELEPHONE: (503) 556-3713 Ext. 496 MONTH JUNE 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 -4 17 -4

~4 2 18 -4

~4 3 19 -5

~4 4 m -4

~4 5 21 -4

~

6 22 -5

~

7 23 -6

~

8 24 -4

~

9 25 -4

~

10 26 -5

-5 11 27 -8

-5 12 28 -9 13 -4 29 -11 14 -4 30 -19 15 -3 31 n/A 16 -3 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

DOCKET NO. 50-344 UNIT SilU1 DOWNS AND FOWER REI)UCTIONS UNIT NAME 'I'roj n n DATE ~7-1 RR COMPLET EI) IlY L- R- Pnt nrnon REPORT MONilg JUNE 1985 TELErtlONE (503)556-3713 Ext. 496

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W. Dave

.! E $g .E Licensee g-( h 8.g'8 cause A Co,,cesive

{ 3g 2 % a: Event aT Action so

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85-03 850502 S 720 C 1 NA BE BE Continued annual refueling outage which began on May 2, 1985.

I 2 3 4 F: F.wced Reason: Method: Exhibit G. instructions S- Scheduled A-Equipment Fallee(Explain) I-Manual for Preparation of Data B Maintenance et Test 2-Manual Scram. Entry Sheets for Licensee C. Refueling 3- Automatic Sc;sm. Event Repewt ILER) File INUREG. >

D-Reguistory Restriction 4-Other (Explain) 0161)

E-Operaint Training A IJcense Exandantion F. Administrative 5 G-Operational Erros (Emplain) ,

Exhibit I Sanw Simree p1G7) IlOthe IEsplain) ,

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Portland General Electric Company Trojan Nuclear Plant P.O. Box 439 Rainier, Oregon 97048 (503)S56-3713 July 8, 1985 WSO-443-85 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 June, 1985.

Sincerol ,

W. S. Orser General Manager WSO/GGB: pat Attachments c: Distribution File: 93.24b I

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