ML20212K986

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Monthly Operating Rept for Oct 1986
ML20212K986
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 10/31/1986
From: Orser W, Ulmer F
PORTLAND GENERAL ELECTRIC CO.
To:
NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
WSO-373-86, NUDOCS 8701290271
Download: ML20212K986 (8)
v • d • e


Text

' OPERATING DATA REPORT DOCKET NO.

50-344 DATE 11-s-R6 COMPLETED BY F. J. Ulmer TEl.EPHONE 503-556-3713 Ext. 495 OPERATING STATUS Notes E danged to E We

1. Unit Name:

Trojan Nuclear Plant as of October 1986 based

2. Reporting Period: October 1986 upon summer seasonal effects 3411 and calorimetric correction.
3. Licensed Thermal Power (MWt):

1216 Historical data submitted

4. Nameplate Rating (Gross MWe): with this report to correet 1130
5. Design Electrical Rating (Net MWe): data for feedwater flow e lement 1133
6. Maximum Dependable Capacity (Gross MWe): effects. Ongoing FEFW fouling
7. Maximum Dependable Capacity (Net MWe):

1075 "

8. If Changes Occur in Capacity Ratings (Items Number 3 Through 7) SinceEt Iteport, GSveEn's [a Changes to #6 and #7 based on corrected values'for MDC durino h'ot summer months and effects of new correction factnr for feedwater flow. venturi fouling.

n/a

9. Power Level To Which Restricted,1f Any (Net MWe):
10. Reasons For Restrictions. If Any: n/n .

This Month Yr to.Date Cumulative 745 7296 89112

11. Hours in Reporting Period 55194 745 5636
12. Number Of Hours Reactor Was Critical n n 3887
13. Reactor Reserve Shutdown Hours 74s ss61 54615
14. Hours Generator On.Line ~

~~3249'~

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15. Unit Reserve Shutdown Hours 173189993
16. Gross Thermal Energy Generated (MWH) 2S37776 18235188 841945 5915291 56733607
17. Gross Electrical Energy Generated (MWH) _,

803742 5614414 53705718

18. Net Electrical Energy Generated (MWH) 100 76.2 61.3
19. Unit Service Factor 64.9
20. Unit Availability Factor 100 76.2 100.5 73.1 56.6
21. Unit Capacity Factor (Using MDC Net) 95.5 68.1 53.3
22. Unit Capacity Factor (Using DER Net) 14.6 0 3.4
23. Unit Forced Outage Rate 24.' Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Each):

Annual Refueling Scheduled for Aoril 1. 1987

25. If Shut Down At End Of Report Period Estimated Date of Startup:
26. Units in Test Status (Prior io Commercial Operation): Forecast Achieved n/a n/a INITI4L ClllTICALITY n/a n/a INITI AL ELECTRICITY COMMERCIAL OPER ATION n/a n/a

~ (9/77) 1290271 861031 R ADOCK 05000344 S tgQ PDR O

, _ L .- ,

-s AVERAGE DAILY UNIT POWER LEVEL

-DOCKET NO: 50-344

. UNIT: Trojan

-DATE: 11-5-86 COMPLETED BY: F. J. Ulmer TELEPHONE: 503-556-3713 Ext. 495

- MONTH October 1986 .

. DAY AVERAGE DAILY POWER LEVEL DAY- AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 1078 17 1089 -

2 1081 18 1085 3 1077 19 1087 4 1075 20 1084 5 1073 21 1085 6 1072 22 1086 1073 1069 7 23 1061 8 1075 24 9 1073 25 1069 10 1070 26 1114

  • 11 1085 27 1075 12 1086 28 1079 13 1088 29 1081 14 1086 30 1082 15 1085 31 1080 16 1087
  • Day Light Savings Time 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 whcle megawatt.

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w TROJAN NUCLEAR PLANT DOCKET NO: 50-344

SUMMARY

OF OPERATING EXPERIENCE DATE: 11-5-86 COMPLETED BY: F. J. Ulmer TELEPHONE: 503-556-3713 OPERATIONS:

The Trojan Nuclear Plant began October at full power and remained at full power throughout the month.

On October 1, 1986, at approximately 1615, the diesel driven AFW pump (P-102B) was run for routine testing. The diesel had been running for about 15 minutes when an operator discovered oil spraying from a connection near the' diesel engine turbocharger. The operator immediately shut down the diesel.

Subsequent investigation revealed the lube oil leak resulted from separation of a turbocharger lube oil line from a tee fitting.

Approximately six gallons of lube oil was lost and one turbocharger was damaged.

As a result of the diesel lube oil rupture, the affected AFW pump (P-102B) was declared inoperable. Appropriate repairs and testing were completed in 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. The turbine driven AFW pump was operable while the diesel pump was out of service.

On October 21, 1986, the Trojan Maintenance Department began removing portions of the Turbine Building siding as a result of a re-evaluation of high energy line breaks in the Turbine Building. The re-evaluation demonstrated safety-related components in the Turbine Building may not be protected in the event of a high energy line break. Removing the siding reduces the pressures and temperatures experienced by the safety-related equipment to acceptable levels. This issue is under further evaluation.

On October 24, 1986, the diesel auxiliary feedwater pump failed to start during post-maintenance testing. A broken electrical lead was found in the over-crank relay which prevented the fuel racks from opening. The lead was repaired and the diesel auxiliary feedwater pump was tested satisfactorily and returned to service.

The primary-to-secondary steam generator tube leakage remained at

one-half gallon per day and the secondary condensate oxygen remained at 5 and 3 ppb for the A and B condensate trains, respectively. The reactor coolant system dose equivalent iodine concentration remained at approximately 10% of the Technical Specification limit.

MAJOR SAFETY-RELATED MAINTENANCE:

1. Removal of Turbine Building siding for high energy line break concerns. (See Above)
2. Diesel Auxiliary Feedwater pump repairs. (See Above)
  1. . 4 .

i ' Summary of' Operating Experience ,

f ReportiDate: 11-05-86 c Page 2 LICENSE CHANGES:t 4

Amendment #120

-The amendment rewords.the Surveillance Requirements and. Bases to reflect.

-that the-Trojan ultimate heat sink is the Columbia River with the-

. cooling tower basin serving as the backup.

' OTHER:

- During this period, the NRC fined Portland General Electric $50,000 for a Severity Level III-violation involving the inoperability of~one of the emergency core cooling system (ECCS) subsystems. On March 31,

] 1986, the flow' path for RHR system cold leg injection to two of the

four reactor coolant system loops was isolated for one hour and ten minutes in violation of. Technical Specification requirements. This event emphasized the-importance.of expediting the programs-already initiated to establish. design basis. documents.with accurate system descriptions. A second Severity Level III violation involved an incomplete inspection by a contract quality control (QC) inspector.. '
On May.13, 1986, an NRC inspector observed that a QC inspector failed to properly witness the torquing of the bolts on.the inlet flange for

, . a pressurizer-safety valve as prescribed by the established procedures.

. The NRC determined PGE's corrective action was prompt and extensive

! and no civil penalty resulted.

Included with this report are revised capacity factors based upon historical data. reflecting maximum dependable power rating values for MDC. MDC's were corrected to reflect the effects of feedwater flow' venturi fouling in calorimetric calculations-and seasonal condenser vacuum effects from January 1980 to December 1985. Also,-the maximum

- dependable capacity gross and net values were changed to 1133 19fe and 1075 MWe,-respectively, based upon summer 1986 data and the new routine adjustment for flow element fouling.

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CAPACITY FACTOR CORRECTION TABLE Period Max CF CF CF MM/YY Depend. Cap Month Year Cum 1.

01/80 1068 94.0 94.0 48.8 02/80 1068 90.8 92.4 49.8 03/80 1068 64.0 82.8 50.1 04/80 1068 21.5 67.6 49.5 05/80 1068 . O 53.7 48.4 06/80 1068 . O 44.8 47.3 07/80 1068 26.3 42.1 46.9 08/80 1068 93.8 48.7 47.9 09/80 1068 100.0 54.3 48.9 10/80 1068 98.7 58.8 49.9 11/80 1068 99.9 62.5 50.9 12/80 1068 89.1 64.7 51.6 01/81 1052 88.3 88.3 52.3 02/81 1052 56.2 73.1 52.4 l 03/81 1052 100.2 83.0 53.3 04/81 1052 95.8 86.2- 54.0 05/81 1052 1. 5 68.8 53.1 06/81 1052 . O 57.3 52.2 07/81 1052 30.3 53.4 51.8 08/81 1052 93.8 58.5 52.5 09/81 1052 99.3 63.0 53.3 10/81 1052 70.7 63.8 53.5 11/81~ 1052 99.2 67.0 54.2 12/81 1052 99.2 69.7 54.9 01/82 1065 74.3 74.3 55.2 02/82 '1065 94.7 84.0 55.8 03/82 1065 71.9 79.8 56.0 04/82 1065 . O 59.7 55.2 05/82 1065 . O 47.4 54.4 06/82 1065 . O 39.5 53.6 07/82 1065 . O 33.7 52.9 08/82 1065 15.9 31.2 52.3 09/82 1065 85.5 37.3 52.8 10/82 1065 100.3 43.8 53.4 11/82 1065 79.0 46.9 53.8 12/82 1065 100.5 51.5 54.4

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l CAPACITY FACTOR CORREC TION TABLE 01/83 1055 65.3 65.3 54.5 02/83 1055 .O .33.9 53.9 03/83 1055 .O 22.0 53.1 04/83 1055 .O 16.5 52.5 ,

05/83 1055 .O 13.0 51.9 06/83 1055 .O 10.8 51.3 07/83 1055 11.6 10.9 50.8 08/83 1055 57.2 16.8 50.9 09/83 1055 95.9 25.5 51.4 10/83 1055 98.2 32.9 51.9 11/83 1055 99.8 38.9 52.5 12/83 1055 100.4 44.2 53.0 01/84 1063 99.3 99.3- 53.5 02/84 1063 92.2 95.9 53.9 03/84- 1063 94.9 95.6 54.4 04/84 1063 78.8 92.2 54.7 05/84 1063 .O 72.7 54.1 06/84 1063 .O 60.6 53.5 07/84 1063 .O 51.8 52.9 08/84 1063- .O 45.1 52.4 09/84 1063 .O 40.1 51.8 10/84 1063 48.4 41.0 51.8 11/84 1063 99.7 46.2 52.3 12/84 1063 99.3 50.7 52.7 01/85 1051 97.9 97.9 53.2 02/85 1051 99.6 98.7 53.6 03/85 1051 73.6 90.1 53.8

, 04/85 1051 97.5 91.9 54.2 I 05/85 1051 2. 8 73.6 53.7 06/85 1051 .O 61.0 53.0 07/85 1051 57.0 60.7 53.3 l

08/85 1051 98.3 65.5 53.7 09/85 1050 77.4 66.8 53.9 10/85 1050 98.1 70.0 54.3 11/85 1050 100.6 72.7 54.7 12/85 1050 100.1 75.1 55.1

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N Portland General Electric Company Trojan Nuclear Plant P.O. Box 439 -

Rainier, Oregon 97048 (503)556-3713 November 5, 1986 WSO-373-86 Trojan Nuclear Plant Docket.50-344 I

License NPF-1 Office of Resource Management US Nuclear Regulatory Commission 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 October, 1986.

Sincerely M

W. S. Orser General Manager Attachment c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Lynn Frank, Director State of Oregon Department of Energy

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