ML20149F746

Monthly Operating Rept for Dec 1987

ML20149F746
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	12/31/1987
From:	Olmstead C, Ulmer F PORTLAND GENERAL ELECTRIC CO.
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
CAO-009-88, CAO-9-88, NUDOCS 8801140321
Download: ML20149F746 (6)

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO: 50-344 UNIT: Trojan DATE: January 1488 COMPLETED BY: F.

J.

Ulmer TELEPHONE: 503 ss6-1711 ext 495 MONTH December 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 1104 17

-7 2

1105 18

-15 3

1106 19

-13 4

1060 20

-15 5

1103 21

-15 6

444 22

-16 7

-40 23

-32 8

-40 24 114 9

-38 25 1086 10

-20 26 1110 11

-17 27 1102 12

-11 28 1101 13

-6 29 1103 14

-7 30 1106 15

-7 31 1117 16

-7 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each

.f{M, day in the reporting month. Compute to the nearest whole megawatt.

1. ((

'8801140321 880106 PDR ADOCK 05000344 (9/77)

R DCD

O OPERATING DATA REPORT.

50-344 DOCKET NO.

DATE _Jmar1 1987 i

COMPLETED BY F.

J.

Ulmer TELEP110NE 503-556-3713 Ext. 495 OPERATING STATUS Notes Trojan Nuclear Plant

1. Unit Name:

2. Reporting Period:

December 1987 3411

3. Licensed Thermal Power (MWt):

1716

4. Nameplate Rating (Gross MWe):

1lin

5. Design Electrical Rating (Net MWe):

1111

6. Maximum Dependable Capacity (Gross MWe):

1075

7. Maximum Dependable Capacity (Net MWe):

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

None N/A

9. Power Level To Which Restricted,1f Any (Net MWe):

N/A

10. Reasons For Restrictions.lf Any:

This Month Yr..to Date Cumulative 744 A760 99716

11. Hours in Reporting Period 313 4731.2 61354.2

12. Number Of flours Reactor Was Critical 0

0 3887

13. Reactor Reserve Shutdown Hours

14. Hours Generator On Line 308.5 4631.7 60671.7 0

0 3249

15. Unit Reserve Shutdown Hours 1031137 13914319 191769641

16. Gross Thermal Energy Generated (MWH)

17. Gross Electrical Energy Generated (MWH) 346_411 4603208 62855638 322888 4347772 59529307

18. Net Electrical Energy Generated (MWH) 41.5 52.9 61.1

19. Unit Service Factor 41.5 52.9 64.3

30. Unit Availability Factor 40.4 46.2-56.2

31. Unit Capacity Factor (Using MDC Net) 38.4 43.9 53.0

22. Unit Capacity Factor (Using DER Net) 58.5 10.7 14.0

23. Unit Forced Outage Rate

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

Annual refuelina scheduled for April 1988 N/A

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

36. Units in Test Status (Prior io Commercial Operation):

Forecast Achieved N/A N/A_

INITIAL CitITICALITY INITIAL ELECTRICITY '

N/A N/A COMM EllCIAL OPER ATION N/A N/A (0/77)

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DOCKET NO. - 5 0-3 4 4 UNITSIIUIDOWNS AND FOWER REDUCTIONS UNIT NAME T rn-i n n L

DATE

.T a niin r v 1999 i

W MPLETEDIli n J.

Olmer REPORT MONTil December 1987 TELErilONE 503-556-3713 ext 495

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Ucensee E*

Cause & Currective N...

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Event g'!

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87-07 12/06/87 F

435.5 A

2 87-37

. II A INSTRU A full load rejection from 100%

power occurred when the turbine control load decrease button shorted electrically.

The reactor was manually scrammed at approximately 5% power.

An 18 day forced outage was begun to repair various valves and for administrative reasons.

The turbine control unit was repaired and the generator was ynched to the grid December 24,-1987.

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2 Method:

Exhibit C-Instructions F: Forced Reason:

I-Manual for Preparation of Data S: Scheduled A-Equipment Falfuse(Explain)

B-Maintenance of Test 2-Manual Scram.

Entry Sheets for Ucensee 3 Automatic Se:am.

Event Report (LER) FBe(NUREG.

C-Refueling 0161)

D Regulatory Restriction 4-Other(Explain)

E. Operator Training & Ucense Examination 5

F-Administrative Extilbit I.Same Source G Operational Errog(Expfain) r7/77)

Il-Other (Explaire) i u..._,-.-......n-ev..-_.--#m<w%.

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TROJAN OPERATING REPORT Summary of Operating Experience - December 1987 The plant entered the month in Mode 1 at 100% power.

On December 6 at 1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />, a total loss of electrical load was experienced due to a malfunction in the electro-hydraulic control (EHC) system load decrease push-button.

The reactor was manually tripped from a power level of about 15 megawatts.

Following the reactor trip, the steam-driven auxiliary feedwater ( AFW ) pump failed to automatically start.

The diesel-driven ARV pump automatically started as designed.

The failure of the steam-driven AFW pump was attributed to a loose electrical connection in the auto-start circuitry.

The pump was successfully started manually.

During the troubleshooting and repairs to the EHC system following the reactor shutdown, concerns were raised by management and the NRC on the adequacy of work instructions and apparent procedural noncompliance.

Two senior NRC managers from Region V arrived on December 8 to further review these events.

The plant was maintained in an administrative hold at about 6% power until these issues could be resolved.

Plant startup was authorized on December 9.

During startup, a leak was identified in the south feedwater pump recirculation line and the north feedwater pump trip circuitry was found to be functioning erratically.

Investigation into these problems was initiated.

At 1522, a reactor shutdown was initiated to allow for a Containment bioshield entry to inspect for leaks as evidenced by increasing Containment humidity and sump pump starts.

Mode 3 was entered at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />.

During the Containment inspection, leakage was discovered from alternate charging line check valve 83798 and steam generator blowdown valve SG-008.

A plant cooldown was initiated to repair these leaks.

At 2218 on December 9, the

'A' reactor coolant pump (RCP) number 1 seal leakoff increased to greater than 6 gallons / minute (about 7.5 gallons / minute indicated).

Per Emergency Procedures, an Unusual Event was declared.

The Unusual Event was terminated at 2343.

l Plant cooldown continued with Mode 4 being entered at 2209 on December 10 and Mode 5 being entered at 0540 on December 11.

On December 14, arcing was observed in the south condensate pump i

motor.

The motor was repaired and returned to service on December 23.

i

e During valve stroke testing on December 16 and 17, safety injection system valves MO-8801A/B, MO-8802A/B, and MO-8835 failed to stroke completely.

Torque switch settings were evaluated and adjusted as necessary, along with valve packing adjustments as required, and the valves retested satisfactorily.

Plant heatup commenced on December 22 with Mode 4 being entered at 0410 on December 23.

The reactor was made critical at 0912 on December 24 and 100% power attained at 0234 on December 25.

Maintenance The following major maintenance was performed during December:

Replaced the

'A' reactor c:olant pump seals, Repaired a broken shear pin in the

'A service water

strainer, Repaired a leak in alternate charging check valve 83798, Repaired a leak in steam generator blowdown drain valve SG-008, and Repaired a nitrogen leak on the north main transformer.

License Amendments Two Amendments to the Trojan Operating License were received:

Amendment 137 Revised the operability and surveillance requirements for the reactor trip breakers and the manual reactor trip function.

Adds similar requirements for the reactor trip bypass breakers.

These changes were made per direction in NRC Generic Letter 85-09.

Amendment 138 Deletes the Condensate Storage Tank from classification of vital equipment in the Security Plan.

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p Portland General Electric Company f','8o January 6, 1987 49 CAO-009-88 Rainier, Oregon 97048 (503)556 3713 l

l US Nuclear Regulatory Commission Document Control. Desk j

Washington, DC 20555 Gentlemen:

Monthly Operating Report 1

In accordance with the Trojan Nuclear Plant mechnical Specifications. reporting requirements, the Monthly Operating Data Report is submitted for December 1987.

Sincerely, C.

A.

Olmstead General Manager Attachment c

Mr. John B.

Martin Regional Administrator, Region V

-US Nuclear Regulatory Commission Mr. William D. Dixon Acting Director Department of Energy State of Oregon Resident Inspector MOR Distribution

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