ML20214K621

Monthly Operating Rept for Jul 1986

ML20214K621
Person / Time
Site:	Duane Arnold
Issue date:	07/31/1986
From:	Bernard Thomas IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20214K617	List: ML20214K615 ML20214K619 ML20214K621
References
NUDOCS 8608210350
Download: ML20214K621 (6)

Text

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OPERATING DRTA REPORT DOCKET NO. 050-0331 DATE 08-15-86 COMPLETED BY Bradford N. Thomas TELEPHONE 319-851-7309 1

OPERATING STATLS.

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1. Unit Name Duane Arnolo Energy Center

2. Reporting Period July. 1986

3. Licensed Thermal Power (MWt):

1658

4. Nemoplate Rating (Gross MWe):

565 (Turbine)

5. Design Electrical Rating (Net MWe):

538 i

6. Maximum Dependable Capacity (Gross MWe):

54 5' 3-

7. Maximum Dependable Capacity (Not MWe)'s 515 f

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since the Last Report, Give Reasons 1

i

9. Pbwer Level to Which Restricted, if Any (Not MWe):

10. Reasons For Restrictions, if Any i.

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744 5087 100775

12. Number of Hours Reactor Was Critical 744 4227.6 71549.5

13. Reactor Reserve Shutewn Hours 0

42.5 192.8

14. Hours Generator On-Line 744 4316.2 69875.7

15. Unit Reserve Shut &wn Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 1127340 5574487 88180722

17. Gross Electrical Energy Generated (MWH) 376524 1880606 29536667

18. Net Electrical Energy Generated (MWH) 354717 1766771 27663408

19. Unit Service Factor 100 84.8 69.3

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20. Unit Availability Factor 100 84.8 69.3

21. Unit Capacity Factor (Using @C Net) 92.6 67.4 53.3

22. Unit Capacity Factor (Using DER Net) 88.6 64.6 51.0

23. Unit Forced Outage Rate 0

2.7 13.2

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

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25. If Shut Down At End 0f Report Period, Estimated 0 ate of Startup:

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AVERAGE DAILY tmli POWER LEVEL DOCKET NO. 050-0331

. MIT Duane Arnol d Energy Center

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DATE 08-15 COMPLETED BY Bradford N. Thomes TELEPHONE 319-851-7309 MONTH July, 1986

-DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Not)

(MWe-Net) 1 510~

17 463 2

518 18 462 3

515 19 462 4

457 20 4 94 5'

436 21 530 6

478 22 524 7

498 23 503 8

470 24 479 9

520 25 503 10 414 26 401 11 463 27 469 12 450 28 485 13 438 29 491 14 469 30 469 15 450 31 4 90 16 466 INSTRUCTIONS On this format,. list the average dilly unit power level In HWo-Net for each day in the reporting nonth. Compute the nearest whole megawatt.

(9/77)

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Dockot No. 050-0331 UAlt N~'a D-A r ~ ': I d E~~rgy C^tt r Dato 08-15-86 MAJOR / SAFETY RELATED MAINTENANCE C3;pictc0 by Brr "f 'r d N.

Th~

n Te l e p ho n e 319-851-7309 DATE SYSTEM COMPONENT DESCRIPTION 07/05/85 Emergency Diesel Generator (EDG)

Annunciator Power Supply for the Replaced a f ailed Annunciator Power Supply

'B' EDG for the

'B' EDG.

37/14/83 High Pressure Coolant I n j e'et io n Steam Supply Out boar d Isolation Tightened packing gland to eliminate System (HPCI)

Valve (M02239) packing leak.

07/14/85 Reactor Core isolation Cooling Steam Supply Outboar d Isolation Tightened packing gland to eliminate System (RCIC)

Valve (M02401) packing leak.

07/16/86 Reactor Manual Control System RMCS to Ro d B lock Mon i tor Ro d Rep laced a faulty relay in the RMCS to Rod (RMCS)

Select Circuitry Relay C11-Z3-K1 Block Monitor System.

07/27/86 Emergency Diesel Generator Annunciator Power Supply for the Replaced a f ailed Annunciator Power Supply

'A' EDG for the

'A' EDG.

07/28/86 Residual Heat Removal (Low LPCI Piping Snubber Tightened Snubber baseplate bo lt s up wh ich Pressure Coolant injection were discovered loose by Qua lity Contro l (LPCI) Mo de )

inspectors.

e-Dockot N2 050-0331 Unit N0co D +rmo Arnmi d E*croy C nter Date 08-15-86 Comp leted by Bra df or d N.

Thomas Telephone 319-851-7309 REFUELING INFORMATION 1.

Name of facility.

A.

Duane Arnol d Energy Center

.2

. Sche du le d date for= next ref ueling shut down.

A.

February, 1987

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3.

Schedule d date for restart following refueling.

A.

April, 1987 4

Will refueling or resumption of operation thereafter require a technical specification change or other license amen dment ?

Yes A.

Re loa d license submittal B.

A ddi t iona l MAPLMGR curves for new fuel bun dles being I n tro du ce d for Cycle 9 5.

Sche du l e d dat e ( s ) for submitting proposed licensing action an d supporting Information.

A.

October 1986 B.

October 1986 6.

Important licensing consi derations associated with refueling, e.g.,

new or di f f erent fuel des i gn or supplier, unrev i ewe d des i gn or performance ana lys i s metho ds, significant changes in fuel design, new operating p ro ce du r e s.

None 7

The number of fuel assemblies (a) In the core and (b) In the spent fuel storage pool.

A.

a) 368 b) 696 8

The present licensod 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.

A.

2050 9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present license d capacity.

A.

1998

Dsckot N3. 050-0331 Unit NOCO Duonn Arnold En' ray Cnnter D3to 08-15-86 Cocp lotod by Bradf er d N. Theres Telephone 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE

~07/01/86 At the beginning of the month the DAEC was in normal power operation with 510 MWE-Net being provi de d to the grid.

07/04/86 At 1442 hours0.0167 days <br />0.401 hours <br />0.00238 weeks <br />5.48681e-4 months <br /> a 7 day LCO was conservatively entered when the

'B' Emergency Diesel Generator (EDG) overspeed trip and start failure annunciators were received in the control room.

The Diesel was not being run at the time.

Investigation revealed a faulty annunciator power supply was the cause.

The power supply was replaced and the

'B' EDG was dec lare d operab le at 0608 hours0.00704 days <br />0.169 hours <br />0.00101 weeks <br />2.31344e-4 months <br /> on 7/05/86 thus terminating the LCO.

The failure of this annunciator power supply woul d not have prevented the Diesel to auto-start if cal led upon to do so.

h 07/07/86 At 0732 hours0.00847 days <br />0.203 hours <br />0.00121 weeks <br />2.78526e-4 months <br /> a 7 day LCO was entered when the fB' Stan dby Liqui d Control (SBLC) pump was removed from-service for lubrication and Inspection. At 1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br /> the

'B' pump was returned to service and the

'A' pump was removed from service for lubrication and Inspection.

The LCO was terminated at 2036 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.74698e-4 months <br /> with the

'A' pump being returned to service.

07/08/86 At 0704 hours0.00815 days <br />0.196 hours <br />0.00116 weeks <br />2.67872e-4 months <br /> a 7 day LCO was entered when the Electric Fir e Pump was remove d f rom service so numerous fire protection va l ves cou l d be disassembl ed an d c leane d.

At 1814 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.90227e-4 months <br /> the LCO was cancelled when the Electric Fire Pump was returned to service.

07/16/86 At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> the 888 Ro d Block Monitor (RBM) was declared Inoperable when the

'B' RBM was foun d not to be receiving a consistent rod select signal from the Reactor Manual Control System (RMCS).

A relay which Interfaces the two systems was replaced and the '8e RBM system was then returned to service at 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> on 07/18/86 07/27/86 At 2102 hours0.0243 days <br />0.584 hours <br />0.00348 weeks <br />7.99811e-4 months <br /> a 7 day LCO was conservatively entered when the

'A' EDG overspeed trip and start failure annunciators were received in the control room.

The Diesel was not being run at the time, investigation revealed a faulty annunclator power supply was the cause.

The power supply was replaced and the

'A' EDG was declared operable at 0528 hours0.00611 days <br />0.147 hours <br />8.730159e-4 weeks <br />2.00904e-4 months <br /> on 7/28/86 thus terminating the LCO.

The failure of this annunclator power supply woul d not have prevented the Diesel to auto-start it called upon to do so.

07/28/06 At 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> it was discovered that a snubber on the

'A' RHR Heat Exchanger was f o un d to have loose anchor bolts.

The plant entered a 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> LCO for review of the event which was terminated at 0951 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.618555e-4 months <br /> on 7/30/86 when the baseplate anchor bolts were secured and an engineering evaluation was performed which determined the snubber was at all times capable of performing its des i g n function.

07/31/86 At the end of the month the plant was in normal power operation with 490 MWe-Net being provided to the grid.

/

Throughout the month of July, the DAEC was power limited (440 hours0.00509 days <br />0.122 hours <br />7.275132e-4 weeks <br />1.6742e-4 months <br /> requiring a 55 reduction in power) due to high ambient temperatures i

which resulted in con denser vacuum limits.

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