ML20210T759

Monthly Operating Rept for Jan 1987

ML20210T759
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	01/31/1987
From:	Olmstead C, Ulmer F PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
CAO-041-87, CAO-41-87, NUDOCS 8702180300
Download: ML20210T759 (6)

Text

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SUMMARY

OF OPERATING EXPERIENCE DOCKET NO: 50-344 DATE:

COMPLETED BY:

TELEPHONE: 503-556-3713 OPERATIONS:

The plant entered January at 100% power. Plant operation continued at full power until January 6 at 1129 when the plant tripped from low steam generator level coincident with a steam /feedwater flow mismatch. A Maintenance technician had been investigating a problem with the 'B' train main feedwater control oil instrumentation and accidentally shorted a power loop which caused the feedwater pump to trip. Turbine load was promptly decreased by operator action, possibly in parallel with a turbine auto runback signal, but not before the steam generator level approached the steam generator low level setpoint, nominally set at 25%. Also, at this time a Periodic Surveillance Test (PICT 3-2) was being performed that involved placing steam /feedwater mismatch bistables in the tripped condition. The combination of the low steam generator water level coincident with steam / feed mismatch bistables being actuated caused the reactor to trip. Associated with the subsequent plant transient, new indications of condenser tube leaks in the 'B' train occurred. Although no confirmed leakers were found, a total of 79 suspect tubes were plugged in the 'C' shell of 'B' train.

The reactor was again critical at 2156 on January 6 and the plant synchronized onto the grid at 0045 on January 7. Power was increased to 40% - 50% power at which time a delay occurred to allow condenser

'B' train restoration, chemistry impurity cleanup, and core axial flux imbalance correction. Full power was reached at 2035 on January 8.

The primary-to-cecondary steam generator tube leakage remained at one-half gallon per day and the secondary condensate oxygen remained at 3 ppb for each train of water. The reactor coolant system dose equivalent iodine condentration remained at 11.5% of the specification limit.

MAJOR SAFETY RELATED MAINTENANCE:

1. Implemented design modifications to 'B' train emergency diesel generator to prevent field flashing component failures.

2. 'A' train ESF outage occurred for preventative maintenance and testing.

3. 'B' train ESF outage occurred for preventative maintenance and testing.

8702180300 870131 PDR ADOCK 05000344 R PDR

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MISCELLANEOUS MAINTENANCE:

1. Plugged 79 suspect' leaking condenser tubes. (see Operations section)

2. . Repaired digital rod position indication due to failed printed circuit-card.

3. During this period a redesign of the Turbine Building walls was completed to allow the wall tarpolins to be replaced with siding that will swing open to relieve any overpressure' condition.

4. Began advanced work on relocating C-160 auxiliary shutdown panel.

LICENSE CHANGES:

Amendment 122 The amendment modifies Technical Specification (TS)' Sections 3.4.1.1 and 3.4.1.2 with respect to the number of reactor coolant loops required to be in operation in MODE 3 and during low power operation, adds a new survellance requirement to TS 4.4.1.2 regarding control rod drive mechanisms, and incorporates minor editorial changes to the-TS.

Amendment 123 The amendment changes Technical Specifications Sections 4.1.2.3, 4.1.2.4 and 4.5.2.i regarding the surveillance requirements for the emergency

{ core cooling system (ECCS) pumps.

MISCELLANEOUS:

During the month of January a team from the Institute of Nuclear Power Operation performed an evaluation of Trojan departments and activities.

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DOCKET NO. 50-344 UNITSIIUIDOWNS AND POWER REDUCTIONS

'- - UNIT NAME Trninn DATE COMPLETED BY F. 3. In mar REPORT MONTil Januarv 1987 TELErtlONE s01-5s6-1711 Ext. 495 e.

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, .{g 3 jY3 Licensee 'f e, gn, Cause & Cnerecilve No. Date g 3g s jg@ Event gy 93 At:iion to

) H fjE $ 3ge 4 g Report 8r to O u

50 . . Prevent Recurrence O

87-01 01-06-87 F 12.8 G 3 87-01 HH MEC FUN Maintenance worker caused main feedpump trip when governor -

control unit was accidently shorted out during trouble-shooting. This was coincidental with a plant I&C test in progress on steam flow / feed flow mismatch circuit. The plant tripped on a low steam generator water level with indicated steam / feed flow mismatch.

I 2 3 4 F: Forced Reason: Method: Exhibit G. instr'uellons S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data

B-Maintenance or Test 2-Manual Scrum. Entry Sheets for Licensee C. Refueling J Automatic Se:am. Event Report (LER) File (NUREG-D Regulatory Restriction 4-Other (Explain) 0161)

E-Operator Training & Ucense Examination -

F. Administrative 5 G-Operational Errug (Explain) .

Exhibit I .Same Source (9/77) Il Other IExplain) '

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- ' AVERAGE' DAILY UNIT. POWER. LEVEL DOCKET NO: 34 4 -

UNIT: Tro-i an

~DATE:

COMPLETED BY:'F. J.-Ulmer-TELEPHONE:50 3-5 5 6-3713 Ext. 495 MONTH January 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1092 17 1088 2 1084 _ ' 18~ 1085 3 1090 19 1081 4 1090 20 1082 5 1093 21 1086 6 506 22 tog 7 7 354 23 1086 8 598 24 1080 9 1082 25 1077 10 1085 26 1076 11 1084 27 ~1085 .

12 1081 28 1085-13 1084 29 1081 14 1083 30 1072 15 1086 31 1074 16 1094 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)

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. .o OPERATING DATA REPORT DOCKET NO.

50-344 DATE COMPLETED BY F. J. Uimer- ,

TELEPHONE 503-556-3713

-Ext. 495 OPERATING STATUS Trojan Nuclear Plant Notes

1. Unit Nam January 1987

. 2. Reporting Period:

3. Licensed Thermal Power (MWt):

3411

4. Nameplate Rating (Gross MWe): 1216

5. Design Electrical Rating (Net MWe): 1130

6. Maximum Dependable Capacity (Gross MWe):

11ll

7. Maximum Dependable Capacity (Net MWe): 1075

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

none

9. Power Level To Which Restricted,if Any (Net MWe): N/A

10. Reasons For Restrictions,if Any: N/A This Month Yr to.Date Cumulative

!!. Hours In Reporting Period 744 744 91320 733.5 733.5 57356.5

12. Number Of Hours Reactor Was Critical 0 0 3887

13. Reactor Reserve Shutdown Hours 731.2 731.2 56771.2

14. Hours Generator On-Line 0 0 3249

15. Unit Reserve Shutdown Hours

16. Gross Thermal Energy Generated (MWH) 2417699 2417699 180273021

17. Gross Electrical Energy Generated (MWH) 800234 , _ ,

800234 59085097

18. Net Electrical Energy Generated (MWH) 763138 763138 55944673 98.3 98.3 62.2

19. Unit Service Fa: tor 98.3 98.3 65.7

20. Unit Availability Factor 95.4 95.4 57.5

21. Unit Capacity Factor (Using MDC Net) 90.8 90.8 54.2

22. Unit Capacity Factor (Using DER Net)

23. Unit Forced Outage Rate 1.7 17 14.1

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

Annual Refuelina Scheduled forAnril'l. 1987

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

26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION N/A N/A (9/77)

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Portland General Electric Company -

Trojan Nuclear Plant P.O. Box 439 ~ February 5, 1987 Rainier, Oregon 97048 : CAO-041-87

-(503)556-3713 Trojan Nuclear Plant Docket 50344 License NPF-1 US' Nuclear Regulatory Commission Document Control Desk Washington, DC '20555 Gentlemen:

Monthly Operating Data Report In accordance with the Trojan Nuclear Plant Technical Specifications reporting requirements, the monthly operating data report is submitted for January 1987.

Sincerely, 0*0h C. A. Olmstead General Manager Attachment c: Mr. John B. Martin Regional Administrator, Region V US Nuclear Regulatory Commission Mr. David O. Kish I Acting Director Department of Energy State of Oregon l

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