ML20134F755

Monthly Operating Rept for Jul 1985

ML20134F755
Person / Time
Site:	Duane Arnold
Issue date:	07/31/1985
From:	Mineck D, Bernard Thomas IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION (ADM)
References
DAEC-85-730, NUDOCS 8508210239
Download: ML20134F755 (8)

Text

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OPERAVING DATA REFORY a .

DOCKET NO. 050-0331 DATE 08-15-85 COMPLETED BY Bradford Thomas

, TELEPHONE 319-851-7339 OPERATING STATUS --

Notes

1. Unit Name Duane Arnold Energy Center

2. Rep ort ing Per i od July, 1985

3. Licensed Thermal Power (MWt): 1658

4. Nameplate Rating (Gross MWe): 565 (Turbine)

5. Design Electrical Rating (Net MWe): 538

6. Maximum Dependable Capacity (Gross MWe): 545

7. Maximum Dependablo Capacity (Net MWe): 515 -

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

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

10. Reasons For Restrictions, if Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 744.0 3087.0 92015.0

12. Number of Hours Reactor Was Critical 286.4 1060.2 63648.9

13. Reactor Reserve Shutdown Hours 0 0 150.3

14. Hours Generator On-Line 265.7 1038.8 61886.5

15. Unit Reserve Shutdown' Hours 0 0 0 l 16. Gross Thermal Energy Generated (MWH) 218976 _,

1224444 77684379

17. Gross Electrical Energy Generated (MWH) 68273 404123 25991477

18. Net Electrical Energy Generated (MWH) 62682 376335 24332486

19. Unit Service Factor 35.7 20.4 67.3

20. Unit Availability Factor 35.7 20.4 67.3

21. Unit Capacity Factor (Using MDC Net) 16.4 14.4 51.3

22. Unit Capacity Factor (Using DER Net) 15.7 13.8 49.2

23. Unit Forced Outage Rate 0 0 16.7

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

None

25. If Shut Down At End Of Report Period, Estimated Date of Startup: N/A E p d f

~

g (9/77)

AVERAGE DALLY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center DATE 08-15-85 C04PLETED BY Bradford Thomas TELEPHONE 319-851-7339 MONTH July, 1985 DAY AVERAGE DAf LY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) 1 0 17 0 _

2 0 18 0 3 0 19 0 4 0 20 2 9 0 21 72 6 0 22 72 7 0 23 122 8 0 24 169 9 0 25 167 10 0 26 173 11 0 27 200 12 0 28 357

! 13 0 29 463 14 0 30 452 13 0 31 351 13 0 INSTRUCTIONS On this format, list the average dally unit power level in MWe-Net for each day in the reporting month. Compute to 9he nearest whole megawatt.

(9/77) l l

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Dsckot Ns. 050-0331 Unit Name Duane Arnold Energy Center Da te 08-15-85 MAJOR / SAFETY RELATED MAINTENANCE Com p l e ted by Bradford Thomas Telephone 319-851-7339 DATE SYSTEM COMPONENT DESCRIPTION

=

7/02/85 Reactor Wa ter Cleanup Leak Detection Logic installed time delay to prevent sys tem isolation caused by spurious signals.

7/07/85 Reactor Protection (RPS) RPS Feeder Breaker Repaired a f au l ty damping spring on a newly Installed trip coil 7/09/85 Reac tor Pro tec tion RPS Mo tor-Gen era tor Set Replaced Local Power Range Mon i tor operational ampilflers 7/20/85 Reactor Core isolation Coo;8ng RCIC Main Turbine Ca l I bra ti on of tu r b i n e governor components (RCIC) 7/21/85 High Pressure Coolant injection HPCI Deluge Tes t Valve Repaired lesking test valve (HPCl) Deluge Sys tem 7/22/85 Turbi ne Genera tor Main Turbine depaired backup overspeed circuitry.

7/30/85 Reac tor Protec tion Rod Block Monitor (RBM) Repaired "A" channel on RBM l

. _ . . . . . . ~ _ .- - . _ - ... - _ - __ -_._- . -. -. . . _ , _ _ _ . - m-.. .. . .. .

UNIT SHUTDOWNS AND POWER REDUCTIONS Docket No. 050-0331 Unit Naac Dusna Arnold Energy Center Date 08-15 REPORT MONTH July, 1985 Completed by Bradford Thomas Telephone 319-851-7339 m

%C LC C^ N O3GO e U $ o -O $ 5 Licensee - EW ue No. Date $

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$"O Event $3 to O 53 CO Cause sv o

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Report # w en o

cL E I O

O t

1 02/02/85 S 471.5 C 1 - - -

Continued Refuel Outage 2 07/21/85 S 0.9 B 1 Overspeed turbine trip testing i

3 07/22/85 S 5.9 B 1 - - - Tu r bi ne tripped to repair backup overspeed circuitry 4 07/30/85 F 0 A 1 - - -

Power reduction due to ,

! limiting control rod pattern

' with an inoperable Rod Block 1 Monitor channel ,

j i

t 1 2 3 4 F: Forced Reason: Method: Exhibit G-Instructions S: Scheduled A-Equipment Failure (Explain) 1-Manual for Preparation of Data

. B-Maintenance or Test 2-Manual Scram. Entry Sheets for Licensee C-Refueling 3-Automatic Scram. Event Report (LER) File (NUREG-D-Regulatory Restriction 4-Other(Explain) 0161)

E-Operator Training & License Examination F-Administrative 5 G-Operational Error (Explain) Exhibit 1-Same Source (9/77) H-Other(Explain)

Docket No. 050-0331 Unit Name Ouane Arnold Energy Center Date 08-15-85 Completed by Brad f ord Thomas Telephone 319-851-7539 REFUELING INFORMATION 1 Name of facility.

A. Duane Arnold Energy Center

2. Scheduled date for next 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 identified 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.

No.

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 d a te of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

A. 1998 1

Docket No. 050-0331 Unit Name Duane Arnold Energy Centar Date 08-15-85 Completed by Bradford Thomas Telephone 319-851-7339 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 07/01/85 At the beginning of the month the Juane Arnold Energy Center was in the final stages of a refuel and maintenance outage.

07/02/85 At 2156 hours0.025 days <br />0.599 hours <br />0.00356 weeks <br />8.20358e-4 months <br />, the Reactor Water Cleanup (RWCU) system isolated as a result of a momentary spurious signal in the leak detection instrumentation.

(LER 85-023) 07/04/85 At 0852 hours0.00986 days <br />0.237 hours <br />0.00141 weeks <br />3.24186e-4 months <br />, pressurization of the primary containment began in preparation for the integrated Leak Rate Test.

07/07/85 At 1142 hours0.0132 days <br />0.317 hours <br />0.00189 weeks <br />4.34531e-4 months <br />, a full Reactor Protection System trip occurred during loading of the "B" RPS motor-generator set feeder breaker. At the time the cause was suspected to be a low sustained current trip setting. After adjusting the trip setting at 2229 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.481345e-4 months <br />, a full RPS trip again occurred during feeder breaker loading. The cause of both trips was attributed to the breaker having an unattached trip coil inside damping spring.

(LER 85-024) 07/08/85 At 1610 hours0.0186 days <br />0.447 hours <br />0.00266 weeks <br />6.12605e-4 months <br />, a full RPS trip signal occurred during a routine surveillance test. A procedural deficiency had called out an incorrect jumper placement.

(LER 85-025) 07/09/85 At 0850 hours0.00984 days <br />0.236 hours <br />0.00141 weeks <br />3.23425e-4 months <br />, the "A" RPS logic tripped during reenergization of the "B" RPS motor-generator set. The cause of the trip signal was an upscale signal from a Local Power Range Monitor operational amplifier.

(LER 85-034) 07/13/85 At 1847 hours0.0214 days <br />0.513 hours <br />0.00305 weeks <br />7.027835e-4 months <br /> a RWCU isolation signal was received due to removing a temporary surveillance test jumper prior to resetting the isolation logic.

(LER 85-023) l 07/15/85 At 1732 hours0.02 days <br />0.481 hours <br />0.00286 weeks <br />6.59026e-4 months <br />, recirculation flow was increased to increase moderator temperature in anticipation of Reactor Startup.

At 1951 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.423555e-4 months <br /> a RWCU isolation occurred during testing of other systems due to a procedural deficiency which omitted the placement of a jumper to

( prevent RWCU isolation.

(LER 85-023)

07/18/85 At 1222 hours0.0141 days <br />0.339 hours <br />0.00202 weeks <br />4.64971e-4 months <br />, the Mode Switch was placed in the startup position and reactor startup was commenced for shutdown margin testing. The reactor was critical at 1538 hours0.0178 days <br />0.427 hours <br />0.00254 weeks <br />5.85209e-4 months <br />.

t.

l l 07/19/85 At 1933 hours0.0224 days <br />0.537 hours <br />0.0032 weeks <br />7.355065e-4 months <br />, the reactor reached 400 psig in preparation for primary containment walkdown. The reactor was driven suberitical at 2110 hours0.0244 days <br />0.586 hours <br />0.00349 weeks <br />8.02855e-4 months <br />. At 2200 hours0.0255 days <br />0.611 hours <br />0.00364 weeks <br />8.371e-4 months <br /> primary containment ?nspection found several small packing leaks.

l All leaks were repaired and personnel removed from the Drywell on 7/20/85 by 0005 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />.

i _- _ _- -- --- . - - -

t Docket No. 050-0331

., . , Unit Name Duane Arnold Energy Center Date 08-15-85 Completed by Bradford Thomas Telephone 319-851-7339 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE (Continued) 07/20/85 The reactor was returned to critical at 0135 hours0.00156 days <br />0.0375 hours <br />2.232143e-4 weeks <br />5.13675e-5 months <br />. At 0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />, rolling of the main turbine for warm-up In preparation for turbine-generator startup commenced. The mode switch was placed in the run posittor at 1308 The main generator was synchronized to the grid at 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br />.

At 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />, the Reactor Core Isolation Cooling System tripped on fast auto-start during quarterly surveillance testing, commencing a 7-day LCO.

Repairs were complete on 7/24/85 ending the LCO.

(LER 85-028 pending)

At 2358 hours0.0273 days <br />0.655 hours <br />0.0039 weeks <br />8.97219e-4 months <br /> the "C" RHR service water pump became inoperable when its auto-vent valve stuck open. A 30-day LCO was entered. The LCO was cancelled when repales were completed on 7/23/85.

07/21/85 At 0219 hours0.00253 days <br />0.0608 hours <br />3.621032e-4 weeks <br />8.33295e-5 months <br /> control rods were Inserted to reduce power in preparation for turbine overspeed trip testing. The turbine was tripped at 0247 hours0.00286 days <br />0.0686 hours <br />4.083995e-4 weeks <br />9.39835e-5 months <br />.

At 0308 hours0.00356 days <br />0.0856 hours <br />5.092593e-4 weeks <br />1.17194e-4 months <br /> the overspeed turbine trip test was completed. The backup overspeed circuitry failed. The generator was resynchronized to the grid at at 0339 hours0.00392 days <br />0.0942 hours <br />5.605159e-4 weeks <br />1.289895e-4 months <br />.

At 1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br /> the HPCI Deluge. system was declared inoperable when a t.

valve leak was detected. A 14-day LCO was entered. Repairs were coe ated on 7/30/85 and the LCO cancelled.

(LER 85-027 pending) 07/22/85 At 1803 hours0.0209 days <br />0.501 hours <br />0.00298 weeks <br />6.860415e-4 months <br /> power was raduced to remove the Turbine from service for repairs to the backup overspeed circuitry. The main turbine was tripped et 1955 hours0.0226 days <br />0.543 hours <br />0.00323 weeks <br />7.438775e-4 months <br />.

07/23/85 Main turbine repairs were completed at 0148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br />, and the main generator placed back on-line.

07/30/85 At 1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br /> a 24-hour LCO was entered due to one Inoperable channel on the Rod Block Monitor (RBM) system while being in a limiting control rod

, pattern. The 24-hour LCO was cancelled at 1603 hours0.0186 days <br />0.445 hours <br />0.00265 weeks <br />6.099415e-4 months <br /> on 7/31/85 when the channel was declared to be opera bl e.

7/31/85 At 1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br /> a momentary violation of secondary containment occurred when two airlock doors were simultaneously opened.

(LER 85-030 pending)

At the end of the month the plant was in normal operation at 376 MWe (gross).

/

lowa Electric Light and Power Company August 15, 1985 DAEC 7 30 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, 1985 Monthly Operating Report

Dear Sirs:

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

Ja w Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/BNT/kp*

Enclosures File A-118d, TE-5 cc: Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Conrnission U. S. Nuclear Regulatory Commission 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 Conunission Box 2517 Washington, D. C. 20555 (1) Marion, IA 52302 U. S. Nuclear Regulatory Commission 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 1100 Circle 75 Parkway Suite 1500 Atlanta, GA 30339 g

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