ML20206P356

Monthly Operating Rept for Mar 1987

ML20206P356
Person / Time
Site:	Duane Arnold
Issue date:	03/31/1987
From:	Axline J, Mineck D IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION & RESOURCES MANAGEMENT (ARM)
References
DAEC-87-0380, DAEC-87-380, NUDOCS 8704210161
Download: ML20206P356 (9)

Text

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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 04-15-87 COMPLETED BY Jeff S. Ax11ne TELEPHOE 319-851-7600 OPERATING STATUS Notes

1. Unit Name Oueno Arnold Eneroy Center

2. Reporting Period March. 1987

3. Licensed Thermal Power (MWt): 1658

4. Nameplete Rating (Grose 14fe):

565 (Turbine)

5. Design Electrical Rating (Not MWe): 538

6. Maximus Dependable Capacity (Gross MWes $45

7. Maximum Dependeble Capacity (Not NWe):

515

8. If Changes Occur in Capacity Ratings (1tene Number 3 through 7) Since the last Report, Give Reasons:

9. Power Level to Which Restricted, If Any (Not MWe):

10. Reasone For Restrictions, If Any:

This Month Yr-to-Oete Cumulative

11. Hours in Reporting Period 744 2160 106608

12. Number of Hours Reactor Was Critical 277.5 1693.5 76363.8

13. Reactor Reserve Shutdown Houre 0

0 192.8

14. Hours Generator On-Line 275.3 1691.3 74431.9

15. Unit Reserve Shutdown Houre 0

0 0

16. Groes Thermal Energy Generated (MWH) 318463.2 2191651.2 94273844.6

-17. Gross Electrical Energy Generated (MWH) 108405 755235 31613320.0

18. Not Electrical Energy Generated (MWH) 100497.6 705812.9 29610613.0 19.-Unit Service Factor 37.0 78.3 69.8

20. Unit Avellability Factor 37.0 78.3 69.8

21. Unit cepecity Factor (Using IOC Net) 26.2 63.4 53.9

22. Unit Capacity Factor (using DER Net) 25.1 60.7 51.6

23. Unti Forced Outage Rete 0

0 14.6

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

Refuel Outene which beoen March 12. 1987.

25. If Shut Down At End of Report Period, Estimated Dete Of Startup Mid-Mey. 1987

{R04210161 870331 T.E14 (9/77)

R ADOCK 05000331 y%

PDR

AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Ouene Arnold Eneray Center DATE 04-15-87 COMPLETED SY Jeff S. Axline TELEPHONE 319-851-7600 MNTH March 1987 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL

.(MWe-Net)

(MWe-Not) 1 351 17 0

2 386 18 0

3 384 19 0

4 378 20 0

5 377 21 0

6 375 22 0

7 371 23 0

8 372 24 0

9 375 25 0

10 375 26 0

11 371 27 0

12 73 28 0

13 0

29 0

14 0

30 0

15 0

31 0

16 0

INSTRUCTIONS On this format, liet die everage daily unit power level in MWe-Net for each day in the reporting month. Compute the ne: rest whole megewett.

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Dackot Ns. 050-0331 Unit Den 9 Arneld Ennroy Centnr Date 04-15-87 MAJOR / SAFETY RELATED MAINTENANCE Completed By Jeff S.

Arline Telephone 319-851-7600 CATE SYSTEM COMPONENT DESCRIPTION 3-2-87 Control Building Heating and Control Building Chiller ('A' Pressure drop across oil filter measured Ventilation unit) satisfactorily.

'A' Carbon. Bed Sump Motor 3-3-87 Control Building Heating and Checked resistance between leads, all were Ventilation satisfactocy.

3-3-87 Control Building Heating and ese Carbon Bed Sump Motor Checked resistence between leads, all were Ventilation satisfactory.

3-4-87 Primary Containment Primary Containment Valve M02146 Cleened and polished the light contacts.

3-13-87 Reactor Building Crane Shield Block Hoist Chain Checked for chain wear.

Wear wee not excessive.

3-17-87 Emergency Service Water Automatic 8ackwesh Motor Performed megger and inspection satisfactorily.

Primary Containment Torus Inspect torus paint.

3-19-87 Standby Gas Treatment Heater Heater inspection was completed satisfactorily.

3-19-87 Nuclear Boiler 3-20-87 Main Steam Plugs Refurbished main steam plugs and performed function test satisfactorily.

3-21-87

'A' Diesel Generator Standby Diesel Generator Resurfaced outboard slip ring and cleaned inside of generator.

Emergency Service Water

.A' Pump Discharge Check Velve Rebuilt the disc pin.

3-23-87 Feedwater 3-25-87 feedwater Hester Temperature Checked calibration of the transmitter.

No Transmitter g

problems were found.

3-26-87 Reactor Building Heating and Recombiner Area Air Conditioning l Replaced filter.

Ventilation 3-27-87 Primary Containment Isolation Valve Circuit Breaker Tightened load side wiring.

r DMkot C*o. 050-0331 Unit Drnm Arneld Eeroy Cet r Date 04-15-87 MAJORJ AFETY RELATED MAINTENANCE Completed By Jeff S. Axline Telephone 319-851-7600 DATE SYSTEM COMPONENT DESCRIPTION J

'B' Recirculation Pump Generator The breaker was satisfactorily serviced pe r 3-30-87 Reactor Vessel Recirculation en inspection procedure.

'A' Recirculation Pump Generator The breaker was satisfactorily serviced per 3-30-87 Reactor Vessel Recirculation en inspection procedure.

3-1-87 Low Pressure Turbine Removal of the old turbine rotor and Turbine thru installation of old buckets on the new 3-31-87 turbine rotor.

(Ongoing)

Reactor Vessel Recirculation Pipe Welds Inservice Inspection of reactor recirculation system pipe welds.

Primary Containment Isolation Valves Local Leak Rate Testing was being performed on these valves.

Feedwater feedwater Hester Feedwater heater tubes were inspected.

HPCI and RCIC Motor Operated Valves Performed Motor Operated Valve Analysis Testing (MOVATS)~on 24 valves.

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DOCKET NO. 050-0331 UNIT Dunn, Arnold Ennray Center DATE 04-15-87 COMPLETED BY Jef f S.

Ax11ne TELEPHONE 319-851-7600 REFUELING INFORMATION 1.

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for next refueling shutdown.

A.

March 12, 1987 3.

Scheduled date for restart following refueling.

A.

Mid May, 1987 4.

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

Yes A.

Reload license submittal B.

Additional MAPLHGR curves for new fuel bundles being introduced for Cycle 9 5.

Scheduled date(s) for submitting proposed licensing action and supporting information.

A.

Submitted B.

Submitted 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 assemblies (a) in the core and (b) in the spent fuel storage pool.

A.

a) 44 b) 1148 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.

A.

2050 9.

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

A.

1998

e DOCKET NO. U50-0331 UNIT Durni Arnold Energy Center DATE " 87 COMPLETED B' Jeff S.

Auline TELEPHONE 319-851-7600 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 3-1-87 At the beginning of the month the Duane Arnold Energy Center (DAEC) was operating at 635 of-rated power with 351 (MWe-Net) being provided to the grid.

Two Limiting Conditions for Operation (LCOs) were still in affect 0

H2 2 monitor control from February:

'A' Core Spray System and the

'A' panel.

The reactor continued in coast down heading for the cycle 8/9 refuel outage.

3-2-87 At 0753 hours0.00872 days <br />0.209 hours <br />0.00125 weeks <br />2.865165e-4 months <br /> a 7 day LCO was entered when the electric fire pump was taken out of service for planned maintenance.

Maintenance was completed satisfactorily at 1255 hours0.0145 days <br />0.349 hours <br />0.00208 weeks <br />4.775275e-4 months <br /> and the fire pump was declared operable, ending the 7 day LCO.

3-5-87 At 1240 hours0.0144 days <br />0.344 hours <br />0.00205 weeks <br />4.7182e-4 months <br /> a 30 day LCO was entered when the

'A' Torus Level Recorder was taken out of service for planned maintenance.

The unit was calibrated satisfactorily and returned to service at 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br />, ending the 30 day LCO.

3-6-87 At 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br /> a 7 day LCO was entered when the reactor building heating and ventilation system circuit breaker was taken out of service for planned maintenance.

Maintenance was completed satisfactorily at 2049 hours0.0237 days <br />0.569 hours <br />0.00339 weeks <br />7.796445e-4 months <br /> and the breaker was put back into service, ending the 7 day LCO.

3-12-87 At 0405 hours0.00469 days <br />0.113 hours <br />6.696429e-4 weeks <br />1.541025e-4 months <br /> reactor shutdown commenced in preparation for the Cycle 8/9 refuel outage.

At 1117 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.250185e-4 months <br /> the main generator was separated from the grid.

At 1306 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.96933e-4 months <br /> the reactor mode switch was put in the startup position.

At 1333 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.072065e-4 months <br /> the reactor was manually scrammed from approximately 10% of rated power.

On tuis date a Nonconformance Report (NRC) was filed on the remote shutdown panel.

It was determined that the welds in the panel were not qualified.

Methods to qualify these welds are currently being investigated.

(LER 87-008) 3-13-87 At 2013 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.659465e-4 months <br /> the reactor was in cold shutdown which ended the 30 day LCO on the

'A' H202 monitor control panel which was entered on February 26, 1987.

3-14-87 During Local Leak Rate Testing (LLRT) it was found that the Main Steam Isolation Valves (MSIVs) exceeded the allowable leakage rate.

Feedwater check valves were also found to leak excessively.

The valves will be repaired and an acceptable LLRT will be performed before they are returned to service.

(LER 87-005)

e DOCKET NO. 050-0331 UNIT Duann Arnald Ennecy Cantor DATE 04-15-87 COMPLETED BY Jeff G. Axline TELEPHONE 319-851-7600 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 3-18-87 At 1737 hours0.0201 days <br />0.483 hours <br />0.00287 weeks <br />6.609285e-4 months <br /> a momentary voltage transient occurred on the instrument AC bus.

This in turn caused the

'A' Standby Filter Unit (58FU) to initiate as well as causing numerous annunciators to light.

The

'A' S8FU and annunciators were reset and no further problems occurred.

(LER 87-006) 3-26-87 At 0230 hours0.00266 days <br />0.0639 hours <br />3.80291e-4 weeks <br />8.7515e-5 months <br /> defueling of the vessel began.

After encountering minor problems with the refuel bridge, defueling of the reactor was completed at 1755 hours0.0203 days <br />0.488 hours <br />0.0029 weeks <br />6.677775e-4 months <br /> on April 2, 1987.

3-31-87 At the end of the month the DAEC was in the early stages of the Cycle 8/9 outage.

Major maintenance being performed includes:

• Replacement of one low pressure turbine rotor.

Inspection of the Feedwater Heaters.

Inservice Inspection (ISI) of Reactor Recirculation Piping.

Motor Operated Velve Analysis Testing (MOVATs) of 24 HPCI and RCIC Valves in response to IE Bulletin 85-03.

LLRT on all primary containment Isolation valves.

l

Iowa Electric Light and Power Company April 15, 1987 DAEC-87-0380 U. S. Nuclear Regulatory Commission ATTN:

Document Control Desk Washington, D. C.

20555

Subject:

Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 February, 1987 Monthly Operating Report

Dear Sirs:

Please find enclosed the Duane Arnold Energy Center Monthly Operating Report for March, 1987. The report has been prepared in accordance with the guidelines of Regulatory Guide 1.16 and distribution has been made in accordance with DAEC Technical Specifications, Appendix A. Section 6.11.1.c.

Very truly yours, (W

kW-Daniel L. Mineck Plant Superintendent - Nuclear Ouane Arnold Energy Center DLM/JA/go*

Enclosures File A-118d cc: Mr. A. Bert Davis Mr. Phillip Ross Regional Administrator U. S. Nuclear Regulatory Commission Region III Maryland National Bank Building U. S. Nuclear Regulatory Commission Washington, D. C.

20555 (2) 799 Roosevelt Road Glen Ellyn, IL 60137 (1)

NRC Resident Inspector Mr. Robert A. Gilbert Mr. Dennis Murdock Project Manager Central Iowa Power Cooperative BWR Project Directorate #2 Box 2517 U. S. Nuclear Regulatory Commission Cedar Rapids, IA 52406 7920 Norfolk Avenue Bethesda, MD 20814 Mr. Russ Gamble Corn Belt Power Cooperative INP0 Records Center 1300 13th Street North 1100 Circle 75 Parkway Humboldt, IA 50548 Suite 1500 Atlanta GA 30339 Q

liuane Arnold Energv Center

• 3277 IJAEC Itoad

• Palo, lona.52324

• 319 Lil ?GII I

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