ML20132G684

Monthly Operating Rept for Jul 1985

ML20132G684
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	07/31/1985
From:	Orser W, Ulmer F PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF RESOURCE MANAGEMENT (ORM)
References
WSO-510-85, NUDOCS 8510010601
Download: ML20132G684 (7)

Text

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OPERATING DATA REPORT DOCKET NO. 50-344

-DATE A-1'-As COMPLETED BY P 7 "lmer TELEPHONE (sn7iss6-3713 Ext. 495 OPERATING STATUS Notes Troian Nuclear plant.

1. Unit Name:

July 1985

. 2. Reporting Period:

3411

3. Licensed Thermal Power (MWt):

1216 i 4. Nameplate Rating (Gross MWe):

1130

5. Design Electrical Rating (Net MWe):

6. Maximum Dependable Capacity (Gross MWe):

1122 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 9.' Power Level To Which Restricted.If Any (Net MWe):

N/A

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

This Month Yr to.Date Cumulative 744. 5.087.0 7A 1a7 n

11. Hours in Reporting Period 537.2 3.304.6 aA nsn 7

12. Number Of Hours Reactor Was Critical 0.0 0o 7 nn7 a

13. Reactor Reserve Shutdown Hours 475.6 3.225.1 45.560.6

- 14. Hours Generator On.Line 3,249.

0.0 0.0

15. Unit Resene Shutdown Hours 1.474.843_n 10.677,221.0 144.663.383.0

16. Gross Thermal Energy Generated (MWH) 475,460.O, 3,417,954. 46,973,734.0

17. Gross Electrical Energy Generated (MWH) 44,394,757.0 444,973.0 3,244,227.

18. Net Electrical Energy Generated (MWH) 63.9 63.4 58.3

19. Unit Service Factor 62.5 63.9 63.4

20. Unit Availability Factor 52.6 s

55.4 59.1

21. Unit Capacity Factor (Using MDC Net) **4 #*d

• 9

22. Unit Capacity Factor (Using DER Net) * * "*

23.' Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type. Date, and Duration of Each1:

25. If Shur Down At End Of Report Period. Estimated Date of Startup: N/A I 26. Units in Test Status (Prior to Commercial Operation): Forecast Achieved N/^ M/A INITIAL CRITICALITY INITIAL ELECTRICITY N/A N/A N/A N/A COMMERCIAL OPER ATION B510010601 850701 l

PDR ADOCK 05000344 PDR r

d-C M4 (9/77)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO:50-344 UNIT: Trojan DATE:8-1-85 COMPLETED BY: F. J. Ulmer TELEPHONE: ( 503 ) S 56-3713 Ext. 495 MONTH July 1985 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 -18 17 1052 2 -14 18 1037' 3 -33 19 1032 4 -33 20 296 5 -33 21 -18 6 1 22 -29 7 222 23 -33 8 447 24 -33 652 9 54[ 25 10 '/ 0 ' 26 1047 11 1034 27 1050 12 1044 28 1048 ,

13 1065 29 1059 14 1056 36 1063 15 1032 31 1056 16 981 l

l 1

l l

INSTRUCTIONS l

On this fomat, list the average daily unit power level in MWe-dur for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

DOCKET NO. 50-344 UNIT SIIU1 DOWNS AND POWER REDUCTIONS UNIT NAME 'T'en i n n DATE R - l R 5 COMPLETED fly P- .T - 111 mn r REPORT MONill July 1985

~ll LErtlONE (507)556-1713 Ext. 495

. ~k -

N.e. Date g

.5 E 3;; hjge

!i f Licensee ,E g h, Cause & Correctivc 3g Event

{7 93 Action to H

$E cE jgg Report *r in U

]O Prevent Recurrence 6

85-03 850502 S 144.9 C 1 NA NA NA 1985 Refueling Outage 85-04 850706 S 5.4 B 4 NA NA NA Turbine-Generator Test'ing Reactor Remained Critical 85-05 850720 F 118.1 A 3 85-09 EB TransF Iligh Winding temperatures on Uni :

Auxiliary Transformer due to failure of transformer cooling system caused an electrical bus /

main generator lockout. The lockout caused a turbine trip /

reactor trip from 100% power.

Following the trip the diesel Auxiliary Feedwater pump tripped on low suction pressure after starting automatically. The uni auxiliary transformer was repairi ed and special plant test were perf< >rmed on the Auxiliary Feedwater pumps to optimize valve settings and control

, y system sgttings.

F- Forced Reason: Method: Exhibit G - Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3 Automatic Sc:am. Event Report (LER) FileINUREG-D-Regulatory Restaletion 4 Other (Explain) 0161)

E-Operator Training & License Examination I Administrative 5 G Operational Errog (Explain) Exhibit I - Same Source 19/77) Il Other (Explaisi)

SURRIARY CF OPERATING EXPERIENCE DOCKET NO: 50-344 DATE: 8-1-85 COMPLETED BY: F. J. Ulmer TELEPHONE: 503-556-3713 OPERATION:

See Attached i

4 MAJOR SAFETY-RELATED MAINTENANCE:

2

1. Completed auxiliary feedwater pump auto-start operational reliability testing.

2. Corrected 'A' RTD bypass (Th)'line blockage at valve.

MISCELLANEOUS MAINTENANCE:

I South main transformer #4' oil circulation pump was repaired.

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LICENSE CHANGES:

l None l

MISCELLANEOUS:

l 1. Stopped several condenser air leaks l

2. Replaced two main condenser tube plugs.

Operation The plant began the month of July in Mode 4 and ended the n.onth in Mode 1 at 100% power. On July 1 at 0540 the plant secured heatup and cooled down to Mode 5 to investigate and repair a RTD bypass manifold flow blockage on Loop A. Valve 8067A ('A' RTD bypass isolation valve) was removed, replaced, rewelded, and the RTD bypass flow as tested. satisfactorily. On July 2, the plant began heatup and entered Mode 4 at 0410 and Mode 3 on July 3 at 0850. Hot rod drop testing was completed satisfactorily on July

3. At 2140 a' Reactor Vessel Flange Leakoff high-temperature alarm was received, the inner seal was isolated and the outer seal was valved in. .On. July 4 at 0612 during recovery from the 10-year reactor coolant system class 1 test, A and D RCS loop first-off and second-off drain valves were determined to be leaking and at 0700 an Unusual Event was declared, based on greater than 10 gpm uncontrolled leakage from the Reactor Coolant Drain Tank (RCDT) to the Containment Recirculation Sump via the RCDT relief valve.

The RCS loop drain valves were promptly retorqued closed and the leakage stopped. At 0805, the Unusual Event was terminated. On July 4 at 1630, the plant entered Mode 2 and the reactor was brought critical at 1712 for Low Power Physics Testing. On July 5 at 1242, the reactor was tripped from zero (0%) power as part of physics testing. At 1940 the turbine-generator unit was syn-chronized onto'the grid and at 2350 the unit was disconnected from the grid as part of turbine generator testing. On July 7 at 0513, the turbine generator unit was again resynchronized with the grid. Reactor power was then increased at 3% per hour to 35%, 45%,.50%, and 75% with holds and 10% power reductions for physics testing.

On July 10 as reactor' power was increased to 99%, various high steam flow safety injection bistables began to actuate. Reactor power was limited to less than 98%, while investigating the prob-

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lem. The high steam flow safety injection setpoints were checked and the setpoints were recalibrated. Also,. condensate oxygen levels increased following the return-to power. Special teams were setup to test all condenser penetrations. Numerous small air leaks were found around the condensers and two major air leaks were found on the 'B' condensate pump suction expansion joint and the southeast bottom corner of the 'A' condenser foundation mount. As part of the process in indentifying oxygen source, power was reduced to 90% on July 11 at 1956. At 2030 condensate oxygen had decreased and power returned to 99%.

Due to warm weather conditions, the main transformer and the auxil-iary transformer unit experienced high temperatures. Additional cooling of the transformers'was instituted by spraying water on the tranformer cooling units. Spraying the coolers with water began on July 10 and continued through the month whenever trans-former temperatures approached undesirable levels.

1

hon July 16 at 2200, reactor power was reduced to 23% to allow a containment entry into the reactor bioshield area to investigate and correct a high/ low oil level alarm on 'C' reactor coolant pump. RCP bearing oil. level was found high and it was lowered to the correct level. .The reactor was returned to full power on July 17 at 0325.

On July 20 at 0706, the reactor tripped from 100% power. The trip was caused.by a short. circuit in the auxiliary transformer unit cooling system which tripped all of the oil circulation pumps and cooling fans. The auxiliary transformer then tripped on high winding temperature causing an electrical bus generator lockout.

The generator lockout tripped the main turbine and caused a reactor

. trip. After the reactor trip, the diesel auxiliary feedwater pump started automatically and then tripped due to low suction pressure.- The diesel AFP suction trip was blocked.by the control room operator and the pump restarted however, its start caused the turbine AFP which had been operating to trip on low suction pressure. The auxiliary transformer problem was corrected and the reactor was brought critical on July 20 at 1447. At 1734 the reactor was manually shutdown aue to high sodium and calcium in the condensate system. Further investigation reveale.d a con-denser tube leak. A tube plug on the 'B' train outlet of 'C' condenser shell had become dislodged during the turbine trip and subsequent condenser pressure transient. On July 21 at 1830, the plant began a cooldown to Mode 4 to facilitate main condenser repairs and allow secondary.. water chemistry cleanup. In order to maintain uninterrupted auxiliary feedwater pump operation during auto starting,-tests were conducted on both pumps to determine discharge valve positioning, required' net positive suction head, and optimum-time delay for suction pressure trips.

On July 21 at 1035, the plant entered Mode 3 and criticality was attained at 2233 on July 24. The turbine generator was synchron-ized at 0502 on July 25. The plant returned to full power and remained there through the end of July.

M f

b.

' Docket No. 50-344

, DIte: 8-1-85 Completed by: G. G. Bair Telephone: (503) 556-3713 X-234 9

REFUELING INFORMATION REQUES_T_

l. Name of facility: Trojan Nuclear Plant

2. Scheduled date for next refueling shutdown: April 1986

3. Scheduled date for restart following refueling: June 1986

4. Will refueling or resumption of operation therc.af ter require a techni-cal specification change or other license amendment? Probably Not If answer is yes, what, in general, will these be?

If answer is no, has the reload fuel design and core configuration been reviewed by your Plant Safety Review Committee to determine whether any unreviewed safety questions are associated with the core reload (Reference 10 CFR Section 50.59)?

If no such review has taken place, when is it scheduled?

5. Scheduled date(s) for submitted proposed licensing action and supporting information: n/a

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures:

none

7. The number of fuel assemblics (a) in the core and (b) in the spent fuel storage pool:

a) 193 b) 340

8. The present licensed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been requested or is planned, in number of fuel assemblies:

1408 No Expansion Planned

9. The projected date of the last refueling that can be discharged to the spent fuci pool assuming the present licensed capacity:

l 2004 L K- __ - - - - ~ - . - --

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N Ponland General Electric Company Trojan Nuclear Plant P.O. Box 439 Rair.ier, Oregon 97048 (503)55.6-3713 August 7, 1985 WSO-510-85 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

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is submitted for July, 1985.

Sincerel ,

/

W. S. Orser

. General Manager M

WSO/GGB/FJU: pat Attachment c: Distribution File 93.2b

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