ML20095D661

Monthly Operating Rept for Jul 1984

ML20095D661
Person / Time
Site:	Duane Arnold
Issue date:	07/31/1984
From:	Mineck D, Putman K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DAEC-84-515, NUDOCS 8408230429
Download: ML20095D661 (8)

Text

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OPERATING DATA REPORT DOCFET NO. 050-0331 DATE 8-15-84 COMPLETED BY Ken S.Putnam TELEPH0fE 319-851-7456 OPERATING STATUS Notes

1. Unit Name - Duane Arnold Energy Center

2. Reporting Perlod July, 1984

3. Licensed Thermal Power (HWt):

1658

4. Nameplate Rating (Gross We):

565

5. Design Electrical Rating (Not MWe):

538

6. Maximum Dependable Capacity (Gross We):

545

7. Maximum Dependable Capacity (Not MWe):

515

8. If Changes Occur in Capacity Ratings (stems Number 3 Through 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 744.0 5111.0 83255.0

12. Number of Hours Reactor Was Critical 705.0 3733.5 5 % 85.0

13. Reactor Reserve Shutdown Hours 0.0 150.3 150.3

14. Hours Generator On-Line 691.1 3621.6 58064.5

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gruss Thermal Energy Generated (MWH) 1031560 5300217 73048779

17. Gross Electrical Energy Generated (MWH) 340073 17853',6 24479413

18. Not Electrical Energy Generated (MWH) 319515 16814 %

22920087

19. Unit Service Factor 92.9 70.9_

69.7

20. Unit Availability Factor 92.9 70.9 69.7

21. Unit Capacity Factor (Using MOC Net) 83.4 63.9 53.5

22. Unit Capacity Factor (Using DER Not) 79.8 61.2 51.2

23. Unit Forced Outage Rate 7.1 17.9 17.3

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, no Duration of Each):

J j

Maintenance Outage September 28 to October 21, 1984 8408230429 840731 5

DR ADOCK 05000333 i

PDR

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

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AVERAGE DAILY UNIT POWER LEVEL s

DOCKET NO. 050-0331 t, NIT Duane Arnold Energy Center DATE 8-15-84 COMR.ETED BY Ken S. Putnam TELEPHONE 319-851-7456 MONTH July, 1984 DAY

AVERAE DAILY POWER LEVEL DAY AVERAE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 280 17 406 2

422 18 498 3

460 19 493 4

497 20 489

-5 499 21 482 6

502 22 467 7

503 23 501 8

484 24 487

+

s.,

9 480 25 498 10 486 26 499 11 496 27 498 12 490 28.

490 13 17 5

.+; 29 363 14 0

30,_

443 15 40 31 494 16 400 INSTRUCTIONS I

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

(9/77) n gw I

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UNIT SHUTDOWNS AND POWER REDUCTIONS Docket No.

050-0331 Unit Name Duane Arnold Energy Center Date 8-15-84 REPORT MONTH July, 1984 Completed by Kenneth S.

Putnam Telephone 319-851-7456 Licensee Cause & Corrective No.

Date Event Action to Report #

Prevent Recurrence 6

07-13-84 F

52.9 H

3 LER 84-027 JC JC-PS Jarred instruments resulted in LER 84-028 FK spurious high reactor pressure signals and resultant scram.

During startup degraded vo lt a ge offsite power grid resulted in a second scram.

7 07-29-84 S

O H

1 None Rod manipulation required reduction in power to 50%.

Rate of increase in power was limited by the preconditioning l

process.

Computer di f f icu lt ies with the periodic core performance summary report delayed the preconditioning process.

1 2

3 4

F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data 8-Maintenance or Test 2-Manual Scram.

Entry Sheets for Licensee C-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREGe D-Regulatory Restriction 4-Other(Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 Exh i bi t 1-Same Source G-Operational Error (Explain)

Docket No.

050-0331 Unit Duane Arnold Energy Center Date August 15, 1984 MAJOR SAFETY RELATED MAINTENANCE Completed by Kenneth S.

Putnam Telephone 319-851-7456 DATE SYSTEM COMPONENT DESCRIPTION 07-02-84 RCIC Drain Pot Bypass Valve CV-2409 Steam leak.

Valve repacked.

07-12-84 Diesel Fire Pump Pump Minimum Flow Valve PSV-3300 The seat of the valve was machined to stop leakage.

07-12-84 Standby Filter Unit Damper Positioners AV-7318A and B Replaced positioner.

(LER 84-026)

Standby Filter Unit Radiation Monitor 6101A Repaired internal electronics. (LER 84-026) 07-26-84 Torus to Reactor Building Air line to CV-4304 Leaking instrument air line replaced.

Vacuum Breaker

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2 Docket No. 050-0331 Unit Duane Arnold Energy Ctr Date August 15, 1984 Completed by Kenneth Putnam Telephone 319-851-7456 REFUELING INFORMATION 1.

Name of facility.

A.

Duane Arnold Energy Center 2

Scheduled date for next refueling shutdown.

A.

February, 1985 3.

Scheduled date for restart following refueling.

A.

May, 1985 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~lntroduced for Cycle 8 5.

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

August, 1984 6

Important licensing considerations associated with refueling, e.g.,

new or different fuel design or supp ler, unreviewed design or performance analysis methods, significant chanjes 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) 576 8

The present Ilconsed spent fuel pool storage capacity and the size of any increase in licensed storage capacity that has been req u es ted 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 Y

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Docket No. 055-0331 Unit Duane Arnold Energy Ctr Date August 15, 1984 Completed by Kenneth Putnam Telephone 319-851-7456 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 07-01-84 Normal plant operation at 45 MWe (gross) and increasing.

07-03-84 At 0535 hours0.00619 days <br />0.149 hours <br />8.845899e-4 weeks <br />2.035675e-4 months <br />, testing of the "A"

Standby Liquid Control pump found the flow rate apparently less than required. A 7-day LCO was declared. The "B" SB LC pump was similarly tested and also found to apparently fall the flow rate requirements.

A 24-hour LCO was entered at 1717 hours0.0199 days <br />0.477 hours <br />0.00284 weeks <br />6.533185e-4 months <br /> and an Unusual Event was declared.

At 2140 hours0.0248 days <br />0.594 hours <br />0.00354 weeks <br />8.1427e-4 months <br /> the "A " pump was found operable with the "B " pump Isolated ending the 24-hour LCO.

07-04-84 At 0250 hours0.00289 days <br />0.0694 hours <br />4.133598e-4 weeks <br />9.5125e-5 months <br /> a Drywell to Torus vacuum breaker CV-4327G was declared inoperable when It failed to close immediately.

CV-4327G was closed within 45 minutes and increased surveillance of operable vacuum breakers was initiated.

07-05-84 Both Standby Liquid Control pumps satisfactorily met the flow rate requirements ending the 7-dsy LCO at 1247 hours0.0144 days <br />0.346 hours <br />0.00206 weeks <br />4.744835e-4 months <br />.

A clerical error In the calculations of the procedure had caused the test failure.

Both pumps were operable.

1 07-09-84 The Diesel fire pump (IP-49) failed to meet the required discharge flow rate and pressure requirements.

A 7-day LCO commenced at 0203 hours0.00235 days <br />0.0564 hours <br />3.356481e-4 weeks <br />7.72415e-5 months <br />.

07-10-84 At 0430 the "A"

Standby Filter Unit for Control Room habitability Initiated on a spurious high radiation signal.

(LER 84-020)

(LER 84-026)

The radiation detector on the "B"

Standby Filter Unit would not calibrate properly.

A 7-day LCO began at 0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />.

07-11-84 The Diesel Fire Pump was declared operable at 2238 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.51559e-4 months <br />, ending the applicable 7-day LCO.

1 07-12-84 The "A" Standby Filter Unit was declared inoperable when its discharge damper (AV-7318A) would not open.

A 24-hour LCO and an Unusual Event commenced at 0015 hours1.736111e-4 days <br />0.00417 hours <br />2.480159e-5 weeks <br />5.7075e-6 months <br /> due to both Standby Filter Units being technically inoperable.

At 0130 hours0.0015 days <br />0.0361 hours <br />2.149471e-4 weeks <br />4.9465e-5 months <br /> the "B " Standby Filter Unit was placed In the tripped condition thereby fulfilling Its safety function and ending the 24-hour LCO and Unusual Event.

At 1355 hours0.0157 days <br />0.376 hours <br />0.00224 weeks <br />5.155775e-4 months <br /> repair of the "A"

SFU was completed.

(LER 84-026)

l, l V Docket No. 055-0331 Unit Duane Arnold Energy Ctr Date August 15, 1984 Completed by Kenneth Putnam Telephone 319-851-7456 NARRATIVE SUHMARY OF OPERATING EXPERIENCE (Cont) 07-13-84

'At 0902 hours0.0104 days <br />0.251 hours <br />0.00149 weeks <br />3.43211e-4 months <br /> the reactor scrammed on a spurious high reactor pressure signal caused'by a jarred instrument rack.

(LER 84-027) 07-14-84 At 0124 hours0.00144 days <br />0.0344 hours <br />2.050265e-4 weeks <br />4.7182e-5 months <br /> the reactor was critical.

At - 0450 hours0.00521 days <br />0.125 hours <br />7.440476e-4 weeks <br />1.71225e-4 months <br /> a leak was d i scove red in the Air Ejector Room and shutdown of the reactor was commenced for repair. At 1524 hours0.0176 days <br />0.423 hours <br />0.00252 weeks <br />5.79882e-4 months <br />, during startup, the reactor scrammed as a result of a degraded voltage condition in the offsite power grid.

At 1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br /> - with the grid sta bi li ty restored, plant loads were transferred from the Diesel Generators to the Startup Transformer and startup commenced.

(LER 84-028) 07-15-84 At 0530 hours0.00613 days <br />0.147 hours <br />8.763227e-4 weeks <br />2.01665e-4 months <br /> the reactor was critical.

At 1555 hours0.018 days <br />0.432 hours <br />0.00257 weeks <br />5.916775e-4 months <br />'the main generator was synchronized to the grid.

07-17-84 The "B" recirculation pump M-G set tripped on low lube oil pressure as a result of a breaker not being fully racked in.

Rea ctor power was reduced and two loop flow restored shortly thereafter.

07-18-84 At 1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br /> a common suction line valve was found closed on the St and by Liquid Control System.

An incorrect valve had been d

inadvertently closed during surveillance testing at approximately

}

104 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

This resulted in an entry into a 24-hour LCO and an Unusual Event.

The valve was immediately restored to the proper pos ition and the Stand by Liquid Control valve lineup was verified.

(LER 84-029) 4 07-26-84 At 1103 hours0.0128 days <br />0.306 hours <br />0.00182 weeks <br />4.196915e-4 months <br /> the air to a Torus to Reactor Building vacuum breaker CV-4304 was isolated causing the valve to f a ll open.

A redundant valve maintained containment Integrity.

A.7-day LCO was commenced for the Inoperability of the va c u u m breaker. At 1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br /> repairs were completed and the vacuum breaker was tested satisfactorily, ending the 7-day LCO.

07-31-84 Normal plant operation at 534 MWe gross.

I

Iowa Electric Iiggnggompany g

DAEC-84 515 f

Director, Office of Inspection 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 July, 1984 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for July, 1984.

The report has been prepared in accordance with the guidel'aes 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.

V truly yours, 7

Daniel L. MtDack Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/KSP/kp*

Enclosures File A-118d, TE-5 cc: Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Commission U. S. Nuclear Regulatory Connission Maryland National Bank Bldg.

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 Marion, IA 52302 Washington, D. C. 20555 (1)

Mr. George Toyne, Gen. Mgr.

V. S. Nuclear Regulatory Commission Corn Belt Power Cooperative ATTN: Mr. M. Thadani Box 508 Phillips Bldg.

Humboldt, IA 50548 Washington, D. C. 20555 INP0 Records Center 1100 Circle 75 Parkway Suite 1500

,d Atlanta, GA 30339

/

Duane Arnold Energy Center e P.O. Box 351 e Cedar napids, Iowa 52406 e 31918517611 J