ML20212G726

Monthly Operating Rept for Dec 1986

ML20212G726
Person / Time
Site:	Duane Arnold
Issue date:	12/31/1986
From:	Mineck D, Bernard Thomas IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DAEC-87-0030, DAEC-87-30, NUDOCS 8701210147
Download: ML20212G726 (9)

Text

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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 01-15-87 COWLETED BY Bradford N. Thomas TELEPHONE 319-851-7309 0F'ERATING STATUS Notes

1. thit Nane Duane Arnold Eneray Center 2, Reporting Period December, 1986 1

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (&oss MWe):

565 (Turbine)

5. Design Electrical Rating (Not MWe):

538

6. Meximum Dependable Capacity (&oss MWe:

545

7. Maximum Depen &ble Capacity (Not MWe):

515

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

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

10. Reasons For Restrictions, if Any:

This Month Yr-to-Date Cumulative

11. Hours In Reporting Period 744 8760 104448

12. Number of Hours Reactor Was Crltical 445.6 7348.4 74670.3

13. Reactor Reservo Shutewn Hours 0

42.5 192.8

14. Hours Generator On-Line 428.1 7181 72740.6

15. Unit Reserve Shutdown Hours 0

0 0

16. &oss Thermal Energy Generated (MWH) 593194 9475958.8 92082193.4

17. &oss Electrical Energy Generated (MWH) 205071 3202024 30858085

18. Not Electrical Energy Generated (MWH) 192814 3008163.5 28904800.5

19. Unit Service Factor 57.5 82.0 69.6

20. Unit Availability Factor 57.5 82.0 69.6

21. Unit Capacity Factor (Using MDC Net) 50.3 66.7 53.7

22. Unit Capacity Factor (Using DER Net) 48.2 63.8 51.4

23. Unti Forced Outage Rate 0

4.0 14.9

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

Ref uel Outaae scheduled for Mid-March,1987 i

I

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

N/A 8701210147 861231=

(9/77)

' N PDR ADOCK 05000331

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AVERAE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnoid Energy Center DATE 01-15-87 COMPLETED BY Bradford N. Thomas TELEPHONE 319-851-7309 MONTH December, 1986 DAY AVERAE DAILY POWER LEVEL DAY AVERAE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 494 17 0

2 492 18 0

3 491 19 0

4 492 20 0

5 492 21 0

.6 488 22 0

7 485 23 104 8

486 24 273 9

177 25 420 10 0

26 492

'11 0

27 484 12 0

28 482 13 0

29 4 84 14 0

30 457 15 0

3' 493 16 0

INSTRUCTIONS On this format, list the average elly unit power level in MWe-Net for each chy in the reporting month. Compute the nearest whole megawatt.

(9/77)

UNIT SHUT D0!NS AND P@"ER CEDUCTICNS Dsckot C@. 050-0331 Ua l t N3me D"'m Aremad Eceroy Cnn t'r Da te 1/15/87 REPORT MONTH December, 1986 Comp l e ted by Bradford N.

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1/3 86-025 ZZ CON On 12-09-86, Reactor shutdown was commenced &e to NRC concerns with the Environmental Qualification (B)) of primary containment nylon, electrical penetrations. The reactor scrammed (LER 86-025) & ring shutcbwn while unsynchronized to the grid at less than 15 thermal power &e to IRM spikes. The E.Q. electrical butt splice conncctions In question were refurbished and reactor startup commenced 12-22-86 1

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F: Forced Reason:

Method:

Exhibit G-I ns tru c ti on s S: Scheduled A-Equipment Failure (Explain) 1-Manual f or Preparation of Da ta B-Maintenance or Tes t 2-Manual Scram Entry Sheets for Licensee C-Refueling 3-Au toma tic Scram Event Report (LER) File (NUREG-D-Regu l a tory Restriction 4-Other (Explain) 0161)

E-Opera tor Trai ning & License Examination F-Ad mi n i s tra ti ve 5

G-Op era tiona l Error (Explain)

Exhibit 1-Same Source i

(9/77)

H-Other (Explain) l

D2ckGt Nc. 050-0331 Uzit Denn Arm t d Evrgy C o t e r-Date 01-15-87 MAJOR /S AFETY REL ATED M A INTENANCE Completed By Bra dfor d N.

Thomas Telephone 319-851-7309 DATE SYSTEM COMPONENT DESCRIPTION 12-2-85 Containment Atmospheric Control TR4386 (Torus Water Temperature Ref urbishe d Torus Temperature Recor de.-

(CAC)

Recor der )

12-2-86 Resi dua l Heat Removal (RHR)

'A' RHR Minimum Flow Valve Cleaned dirty contacts on overload heaters, (MO-2009) and limit switches 12-5-86 Stan dby Gas Treatment ( S B GT )

Torus Exhaust Control Valve CV4301 Replaced leaking three-way Air Supply Valve 12-5-86 Torus Vacuum Breakers Reactor Bu ll oing to Torus Vacuum Olle d Operator Breaker isolation Valve 12-9-86 Containment Atmospheric Control Torus Level Recor der (LR4384)

Replace d Sli dewire and calibrated recor der.

(CAC)

Neutron Monitoring Source Range Monitor (SRM) 4573C Rep lace d a ba d preregu lator card 02-10 to Safety Related Primary Primary Containment Electrical Replace d an d wrapped Electr.ca l Butt 12-21-86 Containment Electrical Penetration Assemblies Spilce Penetration Assemblies to conform Penetrations with Environmental Qualif ication ( EQ )

Stan dar ds 32-11-86 Neutron Monitoring Interme diate Range Monitor (IRM)

Replaced a faulty Voltage Pre-amp Assembly 4572A Neutron Monitoring

'B' Average Power Range Monitor Replace d a def ect i ve Zener Diode on (APRM)

AuxI l lary_ Car d 12-15-86 Res i dua l Heat Removal (RHR)

RHR S h u t dow n Cooling Suctio9 Replaced defective valve operating motor I n boa r d Isolation Valve (M01908) 12-20-86 Reactor vesss! Recirculation

'A' Recirculation Pump Discharge Changed out Torque Switch Bypass Valve (M04629) t2-24-86 Sta n dby Gas Treatment (SBGT)

'B' Flow Controller (FIC58288)

Replace faulty flow controller

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y DOCK ET NO. 050-0331 UNIT Durno Arnald Ea rgy Center D AT E 01-15-87 COMPLETED BY Bra df ord N.

Thomas T EL EPHON E 319-851-7309 REFUELING INFORMATION 1

Name of facility.

A.

Duane Arnol d Energy Center

-2 Sche du l e d date for next refueling s hut down.

A..

March, 1987 3.

Sche du l e d date for restart following refueling.

A.

May, 1987 4

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

Yes A.

Reload licenso submittal B.

Additional M APLH GR curves for new fuel bun di es being I ntro duce d for Cycle 9 5

Sch e du l e d date(s) for submitting proposed licensing action and supporting Information.

A.

Submitted B.

Submitted 6

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

new or different fuel des i g n or supplier, unreviewed design or performance ana ly s is metho ds, significant changes in fuel design, new operating p roce dures.

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 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 license d capacity.

A.

1998 3

.. ~. _,.. _. _ _ _ _,..,..,,.,,. _, _ _ __

'9 DOCKET N0,'050-0331 p.

UNIT Duenn Arnol d Energy Center

+

DATE'01-15-87 COMPLETED By Bra df or d N.

Thomas TELEPHONE 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 12-1-87 At-the beginning of the month the Duane Arnol d Energy Center was operating at 915 o f rated power with 494 (MWe-Net) being provi de d to the gri d while in the coast down mode.

At 0922 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.50821e-4 months <br /> a 30 day Limiting Con dition f or Operation (LCO)' was entere d' when the Torus Temperature Recor der-was removed f rom service for repair.

The LCO was exito d 2020 hours0.0234 days <br />0.561 hours <br />0.00334 weeks <br />7.6861e-4 months <br /> on 12-2-86 with the.recor der being returned.

to service.

12-5-86 At-0825 hours a.7 day LCO was entered when a Reactor Buil ding to Torus Vacuum Breaker Isolation Valve was removed from service for planned maintenance. The operator was olled and the valve was returned to service at 1123 hours0.013 days <br />0.312 hours <br />0.00186 weeks <br />4.273015e-4 months <br /> with the LCO being terminated at this time.

12-8-86 At 0814 hours0.00942 days <br />0.226 hours <br />0.00135 weeks <br />3.09727e-4 months <br /> a 30 day LCO was entered for repair of Torus Level Recor de r LR-4384C.. A faulty sli dewire was replaced an d the unit was recalibrated.

The recor der was returned to service. at 0813 hours0.00941 days <br />0.226 hours <br />0.00134 weeks <br />3.093465e-4 months <br /> on 12-9-86 The LCO.

stayed in affect as Torus Level Recor der LR-438 58 was removed f rom service at 0815 hours0.00943 days <br />0.226 hours <br />0.00135 weeks <br />3.101075e-4 months <br /> on 12-9-86 A calibration check was performed, the unit was returne d to - service, an d the LCO was exited at 1056 hours0.0122 days <br />0.293 hours <br />0.00175 weeks <br />4.01808e-4 months <br />.

12-9-86 ht 1412 hours0.0163 days <br />0.392 hours <br />0.00233 weeks <br />5.37266e-4 months <br /> Reactor Shut down ha d commenced due to NRC concerns with the Env ironmenta l Qua l i f i cat ion ( EQ ) of Primary Containment Electrical Type-Butt Connectors.

12-10-86 At 0218 hours0.00252 days <br />0.0606 hours <br />3.604497e-4 weeks <br />8.2949e-5 months <br /> the Main Generator was unsynchron ized f rom the grid.

At 0358 hours0.00414 days <br />0.0994 hours <br />5.919312e-4 weeks <br />1.36219e-4 months <br /> the reactor scrammed at less than 15 therma l. power due to IRM spikes.

(LER 86-025) 12-11-86 The replacement and wrapping of Primary Containment Electrical Butt Spilce through Connections to conform to EQ Stan dar ds was performed duri ng th i s time 12-21-86 p e r i o d.

12-12-86 At 1436 hours0.0166 days <br />0.399 hours <br />0.00237 weeks <br />5.46398e-4 months <br /> the

'B' train of the Stan dby Filter Unit (SF U) auto-started on a Control Buil ding Ra diation Monitor downsca le tr i p du e to electricians unintentionally bumping supply breakers during the Installation of an AC Distribution Panel cover.

The supply breakers were re-energize d an d the

B' SFU were secure d.

(LER 86-026) 12-18-86 At 0806 hours0.00933 days <br />0.224 hours <br />0.00133 weeks <br />3.06683e-4 months <br /> following surveillance testing which requires the reactor mo de switch to be p lace d in the Refuel Position, the' switch was returned to the s hut down position, which initiates a Reactor Protection System (RPS) trip of short du r a t i o n.

When resetting this planned trip, an ina dvertent trip of the Reactor Protection System (RPS) occurred. Per design, the Scram Discharge Volume (SDV) high level signal is to be bypassed in or der to allow the RPS trip to be successfully reset without another trip occurring as the SDV fills.

This step was neglected by the operators prior to resetting the RPS logic, resulting In the unplanne d RPS trip.

(LER 86-027)

/

o DOCKET NO. 050-0331 UNIT Duann Arnol d Enerow Cntter DATE 01-15-87 COMPLETED BY Bra df or d N.

Thomas T EL EPHON E 319-851-7309 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 12-22-86 At 0350 hours0.00405 days <br />0.0972 hours <br />5.787037e-4 weeks <br />1.33175e-4 months <br /> Reactor Startup commenced following completion of EQ replacement / repair of Primary Containment Electrical Butt Spilce Connections.

12-23-86 At 0613 hours0.00709 days <br />0.17 hours <br />0.00101 weeks <br />2.332465e-4 months <br /> the Generator was synchronized to the grid.

12-24-86 At 0330 hours0.00382 days <br />0.0917 hours <br />5.456349e-4 weeks <br />1.25565e-4 months <br /> a 7 day LCO was entered when the

'B' train of the Sta n dby gas Treatment ( SB GT ) System f alled a surveillance test.

A flow controller di d not properly control flow In the Auto position. The Flow Controller was replaced an d the system was returned to service after successful post-maintenance testing. The LCO was cancelled at 1632 hours0.0189 days <br />0.453 hours <br />0.0027 weeks <br />6.20976e-4 months <br /> on 12-26-86 12-27-86 At 0501 hours0.0058 days <br />0.139 hours <br />8.28373e-4 weeks <br />1.906305e-4 months <br /> a 7 day LCO was entered due to problems with the

'A' Emergency Diesel Gen era to.- Fu e l O i l Transfer Pump Start Stop logic.

Investigation revealed the fuel oil day tank level i n di cat ing switch setpoint had del f te d out of tolerance.

The switch was adjusted an d the system returned to its normal s ta n dby status.

The LCO was exited at 1304 hours0.0151 days <br />0.362 hours <br />0.00216 weeks <br />4.96172e-4 months <br />.

12-29-86 At 0705 hours0.00816 days <br />0.196 hours <br />0.00117 weeks <br />2.682525e-4 months <br /> the Electric Fire Pump was removed from service for preventive maintenance.

This placed the plant in a7 day LCO.

Maintenance was comp leted an d the pum, was returned to service at 1112 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.23116e-4 months <br /> with the LCO being terminato d at this time.

At 0749 hours0.00867 days <br />0.208 hours <br />0.00124 weeks <br />2.849945e-4 months <br /> a 7 day LCO was entered to perf orm the Control Room Stan dby Filter Unit (SFU) Charcoal Bed Deluge System Operability test on the

'A' train.

At 0927 hours0.0107 days <br />0.258 hours <br />0.00153 weeks <br />3.527235e-4 months <br /> the

'A' train was returned to service and the

'B' train was removed from service for testing.

At 1111 hours0.0129 days <br />0.309 hours <br />0.00184 weeks <br />4.227355e-4 months <br /> the

'B' train was returned to service and the LCO was exited.

12-30-86 At 0738 hours0.00854 days <br />0.205 hours <br />0.00122 weeks <br />2.80809e-4 months <br /> a 7 day LCO was entered when the

'A' train of the S ta n dby Gas Treatment (SBGT) System was removed f rom service for the Charcoal Bed Deluge System Operability test.

The

'A' train was returned to service at 0952 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.62236e-4 months <br /> an d the

'B' trai n was remove d f rom service for testing.

At 1307 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.973135e-4 months <br /> the LCO was terminated when the SBGT system was returned to its normal stan dby status.

12-31-86 At the end of the month the DAEC was operating at approximately 90% of rated thermal power with 493 (MWe-Net) being provi de d to the grid.

s

y.

Iowa Electric Light and Power Co npany January 15, 1987 DAEC-87-0030 Director, Offi oi spection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attn: Document Control Desk

Subject:

Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 December, 1986 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for December, 1986. 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 and Regulatory Guide 10.1.

Very truly yours, Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/BNT/pl*

Enclosures File A-118d cc: Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Comission U. S. Nuclear Regulatory Comission Maryland National Bank Building Region III Washington, D. C.

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

NRC Resident Inspector Director, Office of Management and Mr. Dennis Murdock Program Analysis Central Iowa Power Cooperative U. S. Nuclear Regulatory Commission Box 2517 Washington, D. C. 20555 (1)

Cedar Rapids, IA 52406 Mr. Robert A. Gilbert Mr. Russ Gamble Project Manager Corn Belt Power Cooperative BWR Project Directorate #2 1300 13th Street North U. S. Nuclear Regulatory Commission Humboldt, IA 50548 7920 Norfolk Avenue Bethesda, MD 20814 INPO Records Center 1100 Circle 75 Parkway Suite 1500 Atlanta, GA 30339 glf Duane Arnold Energy Center

• 3277 UAEC lload

• Palo, Iowa 82324

• 319 351-7611 e