ML20209E788

Monthly Operating Rept for June 1986

ML20209E788
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/30/1986
From:	Orser W, Ulmer F PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
WSO-221-86, NUDOCS 8609110356
Download: ML20209E788 (6)

Text

_

w OPERATING DATA REPORT DOCKET NO. 50-344 DATE 7/3/86 COMPLETED BY F.

J.

Ulmer TELEPHONE sn'_ss6-3713 OPER ATING STATUS otes

1. Unit Name:

Troian Nuclear Plant June 1986

, 2. Reporting Period:

1411

3. Licensed Thermal Power (MWt):

1216 4.. Nameplate Rating (Gross MWe):

1130

5. Design Electrical Rating (Net MWe):

1100

6. Maximum Dependable Capacity (Gross MWe):

1050

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 N/A

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

10. Reasons For Restrictions.If Any:

N/A This Month Yr..to.Date Cumulative 720 4343 86159

11. Hours in Reporting Period 303.2 2810.2 52360

12. Number Of Hours Reactor Was Critical n

n un 7

13. Reactor Reserve Shutdown Hours 245.8 2751 51805

14. Hours Generator On.Line 0

0 1249

15. Unit Reserve Shutdown Hours 703740 8751C~17 163706482

16. Gross Thermal Energy Generated (MWH) 225670 279812R 53616444

17. Gross Electrica! Energy Generated (MWH) 704710 7646474 5071777R

18. Net Electrical Energy Generated (MWH) la 1 61 1 6n 1

19. Unit Service Factor 34.1 63.3-63.9

20. Unit Availability Factor 27.0 58.0.

54.6

21. Unit Capacity Factor (Using MDC Net) 75 1 5119 57 1

22. Unit Capacity Factor (Using DER Net) 14.0 2.0 15.0

23. Unit Forced Outage Rate

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

None-N/A

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

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

Forecast Achieved N/A N/A INITIAL CRITICALITY N/A N/A INITIAL ELECTRICITY N/A N/A COMMERCIAL OPERATION 8609110356 860630 N77)

DR ADOCK 05000344 PDR

/'//

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:

50-344 UNIT:

Tro-ian DATE:

7/3/86 COMPLETED BY: p-

.1 _ t ri mo r TELEPHONE: (5031556-3713 (Extension 495)

MONTH aunn 1986 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1

-6 17

-34 2

-5 18

-28 3

-5 19

-27 4

-5 20

-6 5

-10 21 262 6

-9 22 493 7

_7 23 962 8

-25 24 1029 9

-32 25 1057 10

-28 26 781 11

-18 27 1060 12

-18 28 1069 13

-14 29 1075 14

-14 30 1070 15

-28 31 N/A 16

-33 INSTRUCTIONS j

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.

l 1

(9/77)

i i

I UNIT SHUTDOWNS AND POWER REDUCTIONS DOCKET NO. 50-344 1

ll UNIT NAME Trn%n DATE 7/3/RA COMM.TED BY r 7

n ' asm e REPORT MONTil June 1986 TELEPif0NE (soliss6-1717

{

(Extension 495)*

i

5. E 3

h.Eh Ucensee

,E

• Cause & Corrective Date g

• 3g s

,g g &

Event g7 63 Action to yO Prevent Recurrence f~

jg Report se en U H

O 86-05 860416 S

430.4 C

1 N/A Eg BB 1986 Refueling Outage 86-06 860619

.F 40.2 G

3 86-07 IA Instru

' Reactor trip during turbine testing due to inadvertently exceeding reduced power range nuclear setpoints.

86-07 860620 S

3.6 B

4 N/A EZ BR Turbine generator testing completed; turbine off line, but reactor remained critical.

l i

a

]

I 2

3 4

i F: Forced Reason:

Method:

Exhibit G Instructions 5: Scheduled A-Equ?pment Falfore(Explain)

I-Manual for Preparation of Data l

B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Ucensee j

C Refreling 3 Ausomatic Se:am.

Event Report (t.ER) File (NUREG.

D Regulatory Restriction 4-01her (Explain) 0161)

E Operatur Training & Ucense Examination F-Adn,inistrative 5

G Operational Errug(Explain)

Exhibit I-Same Source 4

j Pl/77)

II-Other (Explain) 1

o TROJAN NUCLEAR PI ANT DOCKET NO:

50-344

SUMMARY

OF OPERAT7NG EXPERIENCE DATE:

7-3-86 COMPLETED BY:

F.

J.~Ulmer-TELEPHONE:

503-556-3713 OPERATIONS:

The Trojan Nuclear Plant entered the month of June in Mode 5 and ended the month in Mode 1 at 100% power.

On June 6, Trojan commenced a heatup to check Reactor Coolant System (RCS) thermal expansion measurements.

At 0855, the plant entered Mode 4 and on June 9 at 1846 the plant entered Mode 3.

At 0720 on June 11, the plant returned to Mode 4 after taking thermal expansion measurements and entered Mode 5 at 1316 on June-11, to make final shim adjustments to RCS restraints.

The plant completed the adjustments and entered Mode 4 at 1055 on June 15, Mode 3 at 1630 on June 15, and at 1640 on June 16 the plant entered Mode 2 for low-power physics testing.

Initial Cycle 9 criticality occurred at 2030 June 16 and low-power physics testing was conducted.

Or. June 18 at 2235, the main turbine generator unit was synchro-i nized to the grid in preparation for conducting turbine testing.

At 0059 on June 19, the reactor tripped when the reduced power range setpoints were exceeded during the preparation for turbine testing.

The reactor was taken critical again on June 20 at 0322, entered Mode 1 at 1640 and was synchronized to the grid at 1707.

The turbine was taken off line, leaving the reactor critical, on June 20 at 2150, =in order to conduct turbine overspeed and valve tightness testing.

On June 21 at 0123, the turbine generator unit was again synchron-ized to the grid, and the plant commenced power escalation.

At i

1332 June 25, Trojan reached 100% power.

On June 26 at 0255, the plant began power reduction to 20% to i

tighten a leaking reactor coolant loop drain valve.

The plant returned to 100% power at 2100 June 26 and remained at full power through the end of the month.

The reactor coolant system dose equivalent iodine activity was 9.4% of the limit.

The primary-to-secondary steam generator tube leakrate was about one gallon per day.

On the morning of June 25, a turbine high-vibration trip signal actuated and immediately cleared.

The vibration spike was caused by a sensor not riding correctly on turbine shaft.

Although the turbine trip signal occurred, the duration of the signal was not long enough to cause the turbine to actually trip.

The sensor positioning was readjusted.

MAJOR SAFETY-RELATED MAINTENANCE:

1.

Adjusted the reactor coolant system thermal expansion gaps to within correct tolerances.

2.

Satisfactorily completed reactor physics testing of nuclear design parameters.

Actural control rod worth was lower than predicted.

This will be evaluated further.

3.

The throttle valve internals and flow orifices for the contain-ment spray sodium hydroxide addition system were modified to ensure proper additive flow.

This system was satisfac-torily tested per new technical specification acceptance cri-teria.

4.

Due to the reliability concerns, the safety injection flow path throttle valves to the reactor coolant system were modi-fled.

Post-modification flow testing was completed satis-factorily.

A detailed review of other similar valves did not reveal any other concerns.

5.

Auxiliary feedwater pump modifications were completed and post-modification testing of the pumps were completed satis-factorily.

6.

During the month, special testing of the Control Room Emergency Ventilation System (CB-1) was conducted to ensure correct outside air makeup and to ensure that a positive pressure could be maintained in the control room during an accident.

Prior to testing, the outside air makeup filter plenum was modified and the carboh filters were changed out.

MISCELLANEOUS MAINTENANCE:

1.

Satisfactorily completed service water system discharge piping repairs.

Repairs were required due to a ship hitting the discharge pipe on April 11, 1986.

(See LER 86-04) 2.

Flushed service water system supply lines to safety-related auxiliary feedwater pumps and components of A and B component cooling water systems.

LICENSE CHANGE:

Amendment #115 allowed operation to continue for 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> for diagnosis and repair af control rod assemblies for the case where one or more assemblies are electrically inoperable.

Amendment #116 removed the maximum total weight of uranium state-ment from Technical Specification 5.3.1 to allow for changes in manufacturing techniques.

Amendment #117 reinstates the original 4.6.2.2 technical specifi-cation surveillance method f.or the containment spray sodium hydrox-ide addition system.

The surveillance now requires drawing fluid from the sodium hydroxide tank, through the eductors and verifying actual flow.

f i..

d PG amec

• Portland General Electri: Company Trojan Nuclear Plant P.O. Box 439 Rainier, Oregon 97048 (503)556-3713 July 7, 1986 WSO-221-86 Trojan Nuclear Plant Docket 50-344 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 June, 1986.

Sincerel I

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