ML20137J678

Monthly Operating Rept for Dec 1985

ML20137J678
Person / Time
Site:	Duane Arnold
Issue date:	12/31/1985
From:	Mineck D, Putnam K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DAEC-86-0039, DAEC-86-39, NUDOCS 8601230140
Download: ML20137J678 (8)

Text

OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 1-15-86 COMPLETED BY Kenneth S. Putnam TELEPHONE 319-851-7456 OPERATING STATUS Notes

1. Unit Name Duane Arnold Energy Center

2. Reporting Period December, 1985

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (Groc,s MWe):

565 (Turbine)

5. Design Electrical Rating (Not MWe):

538

6. Maximum Dependable Capacity (Gross MWe):

54 5

7. Maximum Dependable Capacity ( %t MWe):

515

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

9. Power Level to Wilch Restricted, if Any (Net MWe):

10. Reasons For Restrictions, if Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744.0 8760.0 95688.0

12. Number of Hours Reactor Was Critical 744.0 4733.2 67321.9

13. Reactor Reserve Shutdown Hours 0

0 150.3

14. Hours Generator On-Line 744.0 4711.8 65559.5

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWW 940744 6146300 82606234

17. Gross Electrical Energy Generated (MWH) 322716 2068707 27656061

18. Net Electrical Energy Generated (MWH) 3035 %

1940486 25896637

19. Unit Service Factor 100.0 53.8 68.5

20. Unit Availability Factor 100.0 53.8 68.5

21. Unit Capacity Factor (Using MDC Net) 79.2 43.0 52.6

22. Unit Capacity Factor (Using DER Net) 75.8 41.2 50.3

23. Unit Forced Outage Rate 0

0 15.9

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

An approximately one week outage for Installation of the auxiliary transformer and to perform annual surveillance tests is tentatively scheduled in April /May, 1986

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

N/A B601230140 851231 DR ADOCK O 31 g p,73 il'

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AVERAGE DAILY UNIT POWER LEVEL j

DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 1-15-85 COMPLETED BY Kenneth S. Putnam TELEPHONE 319-851-7456 MONTH December, 1985 i

f DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(WWe-Net) 1 362 17 400 2

416 18 425 3

413 19 398 4

409 20 410 5

412 21 462 6

414 22 457 7

406 23 448 8

410 24 421 9

411 25 419 10 410 26 417 11 416 27 418 12 412 28 410 13 417 29 413 14 277 30

- 413 15 365 31 415 4

16 401 lNSTRUCTIONS l

On this format, list the average daily unit power level in kWr-Net for each day in the reporting month. Compute 9he nearest whole megawatt.

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UNIT SHUTDOWNS AND POWER REDUCTIONS Docket No. 050-0331 Uni t Name Duane Arnold Energy Cen ter Date 1-15-85 REPORT MONT H December, 1985 Completed by Kenneth S.

Putnam Telephone 319-851-7456 C^

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LER 85-43, BJ ISV Power was reduced to Rev. I approxima tel y 405 to permit a con trol rod sequence exchange. The reduced power levels also facilitated p l a r.n e d ma i n tena nce activities in the steam tu n n e l on a HPCI s team supply i so l a ti on valve.

I 2

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'F: Forced Reason:

Methods Exhi bi t G-Ins tructions S: Scheduled A-Eq u i pmen t Failure (Explain) 1-Manual f or Prepara tion of Da ta B-Maintenance or Test 2-Manual Scram Entry Sheets for Licensee

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E-Operator Training & License Exam ina ti on F-Adm i n i s tra ti ve 5

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Docket No. 050-0331 Unit Name Duane Arnold Energy Center Date 1-15-85 Completed by Kenneth S. Putnam Telephone 319-851-7456 REFUELING INFORMATION 1

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for n6xt refueling shutdown.

A.

1987 3.

Scheduled date for restart following refueling.

A.

1987 4

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

A.

None currently identitled 5.

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

A.

None currently identifled 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) 368 b) 696 l

8.

The present licensed spent fuel pool storage capacity and the size of l

any increase in licensed storace capacity that has been requested or is planned, in number of fuel assemblies.

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The projected date of the last refueling that can be discharged to the

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spent fuel pool assuming the present licensed capacity.

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Docket No. 050-0331 Unit Name Duane Arnold Energy Center D a t e

_1_ 8 5 Completed by Kenneth S.

Putnam Teleph'une 319-851-7456 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 12/01/85 At the beginning of the month, the plant was in normal power opera +lon with 378 MWs gross electricol generation.

Power levels were restricted to conserve fuel per utility fuel burn goals.

At 0802 hours0.00928 days <br />0.223 hours <br />0.00133 weeks <br />3.05161e-4 months <br />, the "A" Control Building Standby Filter Unit suto-started when an associated radiation monitor failed downscale.

(LER 85-47, Rev. O LER 85-47, Rev.

1, Pending) 12/03/85 At 0145 hours0.00168 days <br />0.0403 hours <br />2.397487e-4 weeks <br />5.51725e-5 months <br />, a torus temperature recorder (TR-4386 Pen 1) was found to not properly track torus temperature. A 30 day LCO was entered.

's 12/06/85 Torus temperature recceder (TR-4386 Pen 1) was decle' red operable at 2052 I

hours ending the 30 day LCO.

i 12/09/85 At 1245 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.737225e-4 months <br />, testing of the steam neak detection Instrumentation for the Reactor Core isolation cooling system found the steam supply high flow Instrumentation out of calibration slightly beyond Technical S pe e l f i ca.1 l on

,j values.

The high flow Instrumentation was evaluated as still capable of performing its design function.

Other parameters of steam leak detection Isolation logic were fully operational.

The high flow Instrumentation was3 recalibrated and returned to service.

I 12/11/85 At 1058 hours0.0122 days <br />0.294 hours <br />0.00175 weeks <br />4.02569e-4 months <br />, the "B" Offges Sample Radiation Monitor was found inoperable during testing commencing a 7 day LCO.

Ar 1210 hours0.014 days <br />0.336 hours <br />0.002 weeks <br />4.60405e-4 months <br />, testing of the "B" Standby Filter Unit (SFU) found an exhaust damper (AY-73228) to stick in the open position. Although theidamper itself has no safety function, the "B"

train of SFU was conservatively declared!

Inoperable due to the potential for partial system flow loss.

A 7 day L C,0 commenced.

i 12/13/85 At 0955 hours0.0111 days <br />0.265 hours <br />0.00158 weeks <br />3.633775e-4 months <br />, the "B" Offges sample Radiation Monitor was returned to service ending the 7 day LCO.

At 2201 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.374805e-4 months <br />, the High Pressure Coolant injection (HPCl) System was voluntarily removed from service to permit planned packing maintenance on a steam supply valve.

(LEP 85-43, Ray.

1) 12/14/85 At 0150 hours0.00174 days <br />0.0417 hours <br />2.480159e-4 weeks <br />5.7075e-5 months <br />, a power reduction to approximately 405 was initiated to permit a control rod sequence exchange.

At 1740 hours0.0201 days <br />0.483 hours <br />0.00288 weeks <br />6.6207e-4 months <br />, a reactor power increase was initiated.

At 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br />, the HPCI system was returned to service ending the 7 day LCO.

12/16/86 At 1023 hours0.0118 days <br />0.284 hours <br />0.00169 weeks <br />3.892515e-4 months <br />, a Torus temperature transmitter (TT 4324) was found inoperable during testing commencing a 30 day LCO.

At 1854 hours0.0215 days <br />0.515 hours <br />0.00307 weeks <br />7.05447e-4 months <br />, the "B" Control Room Standby Filter Unit was returned to service ending the 7 day LCO.

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Doche? No. 050-0331

,f Unit Name Duane Arnold Energy Center Date 1-15-85 Completed by Kenneth S.

Putnam Telephone 319-851-7456 l

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Continued) i 12-17-85 At 1117 hours0.0129 days <br />0.31 hours <br />0.00185 weeks <br />4.250185e-4 months <br />, performance of a manual sensor check of the "A"

Standby j

Filter Unit resulted in an unplanned auto-Initiation of the system.

(LER 85-47) t 12-27-85 At 0908 hour0.0105 days <br />0.252 hours <br />0.0015 weeks <br />3.45494e-4 months <br />, Torus temperature transmitter TT-4324 was returned to service i

i ending the 30 day LCO.

i 12-31-85 At 1635 hours0.0189 days <br />0.454 hours <br />0.0027 weeks <br />6.221175e-4 months <br />, curing testing of the diesel driven fire pump (IP-49), a tube oil line busted spraying oil onto the turbocharger.

A small fire started but was promptly extinguished by operations personnel. The diesel driven fire pump was declared inoperable and a 7 day LCO commenced for repair of-the pump.

At the end of the month, the plant was operating normally at 445 MWe (gross).

As of December 31, the plant has been operating on-line continuously for 161 days.

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Iowa Electric Light and Ibwer Compmy January 15, 1986 DAEC-86-0039 Director, ~0ffice of Inspection and Enforcement

^

U. S. Nuclear Regulatory Commission Washington, D. C.

20555 P

Attn: Doc nent Control Desk

Subject:

Duane Arnold Energy' Center Docket No. 50-331 Op. License DPR-49 December, 1985 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for December,1985.

The report has been prepared in accordance with j

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, es Daniel L. Mineck

(

Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/KSP/kp*

Enclosures File A-118d, TE-5 T

cc: Girector, Office of Inspection Mr. Phillip Ross and Enforcement

. U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Commission Maryland National Bank Building Region III Washington, D. C.

20555 799 Roosevelt Road

' 3 Glen Ellyn, IL 60137 (1)

NRC Resident Inspector Director, Office of Management and Mr. Dennis Murihck Progran Analysis Central Iowa Power Cooperative 5

U. S. Nuclear Regulatory Connission Box 2517 Washington, D.'C. 20555 (1)

Marion, IA 52302 U. S. Nuclear Regulatory CommisMon Mr. Russ Gamble ATTN: Mr. M. Thadani Corn Belt Power Cooperative Phillips Building 1300-13th Street North Washington, D. C. 20555 Humboldt, IA 50548 INP0 Records Center g

V 1100 Circle 75 Parkwaj,'

Suite 1500 S-

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Atlanta, GA 30339 tienenol <![ fire

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• Cnt.tr,lLapitis. lennt 524(Ni

• 319/39&4411

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