Text

Monthly Operating Rept for May 1982
	ML20054G215
Person / Time
Site:	Duane Arnold
Issue date:	06/14/1982
From:	Brown S; IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	;
Shared Package
ML20054G214	List: ML20054G213; ML20054G215;
References
	NUDOCS 8206210279
	Download: ML20054G215 (6)
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OPERATlf!G DATA REPOR7 90CKET NO. _050-0331 DATE June I W 1982 00MrLETED fiY.SidnAyl _ Brown TELEPllONE '414-RR1-5611 '

OPERATING STATUS I. Unit Name.

Duane Arnold Energy Center Notes

2. Rep *orting Period:

May 1982

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (Gross MWe):

Uu M ne Raungb

5. Design Electrical Rating (Net MWe):

538

6. Maximum Dependable Capacity (Gro::s MWe):

545

7. Maximum Dependable Capacity (Net MWe):

515

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

9. Power Level To Which Restricted. lf Any (Net MWe):

10. Reasons For Restrictions.If Any:

This Month Yr.-to.Date Curautative

11. Hours in Reporting' Period 744 3,623 64,247

12. Number Of Ilours Reactor Was Csitical 574.9 3,094.8 46,573.5

13. Reactor Reserve Shutdown Hours 0

'O 0-537.7 3.034.1 45.423.5

14. Hours Generator On-Line

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 623,733.6 4,065,768.4 57,119,166.4

17. Gross Electrical Energy Generated (MWH) 210,837 1,374',428 19,149,468

18. Net E!:ctrical Energy Generated.(MWH) 196.176.8 1.293.428.2 17.925.013.6

19. Unit Sen-ice Factor 72.3 83.7 70.7-

20. Unit Availability Factor 72.3 83.7 70.7

21. Unit Capacity Factor (U>ing MDC Net) 51.2 69 3 __

22. Unit Capacity Factor (Using DER Net) 49.0 66.4 __

54.2 51.9

23. Unit Forced Outage Rate 27.7 6.8 16.5

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

Refueling. Seotember 7. 1982. 8 weeks

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

Turbine Rating:

565.7 MWe Generator Rating:

663.5.(MVA) x.90 (Power Factor) = 597 MWe 8206210279 820614 PDR ADOCK 05000331

. (9p71 i

R PDR

AVERAGE DA!LY UNIT POWER LEVEL DOCKET NO. 050-0331 Duane Arnold UNIT Ernu cantor

~

DATE June 14, 1982 COMPLETED BY.Sid.ney L.. Brown TELEPHONE _319-851-56il MONTig May, 1982-DAY AVER AGE DAILY POWER" LEVEL DAY AVER ACE DAILY POWER LEVEL (MWe Net)

(MWe-Net) 400 37 0

~

2 343 is 0

3 402 39 0

4 419 20 0

5 420 21 0

6 419 22 32 7

407 23 282 h

8 263 24 376 9

19 25 429 10 0

26 458

'11 82 27 460 12 303 456 73 13 323 29 429 14 323 39 305 15 357 3

342 16 90

~

INSTRUCTIONS the nearest who!c merawatt.Oa this fonnat list the average daily unit power levelin Mw o

(9/771

UNITSIIUTDOWNS AND POWER REDUCT10NS DOCKET NO.

050-0331 UNITNAME Duane Arnold Energy Ctv DATE

.lona 14. 1982 REPORT MONT11 May 1982 COMPLETED BY Ririnov i R mwn TELEPl!ONE 319-831-5611 e.

'5._ 5 c

c ci Nii' Date E.

5 _s TSd E C "5 C 5%

Caus: & Corrective

$.2 0

5 g ec Event gg Action to gmp Report #

mO oO e

g Prevent Recurrence a

7 820509 F

53.4 3

Reactor scram caused by generator loss of field.

8 820516 F

152.9 3

Failure of Emergency Bearing Oil Pump resulted in RPS trip and reactor scram. Replaced pump bearing.

I 2

3 4

Fr Forced Reason:

Method:

Exhibit C Instructions S: Scheduled A Equiprnent Failure (Explain)

I Manual for Preparation of Data B Maintenance of Test 2-Manus 1 Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scram.

Event Report (LER) File (NUREG-D Regu! story Restriction 4-Other (Explain) 0161)

E Operator Training & License Examination F-Adm!nistrative 5

G-Ope _:ional Ermr(ExMain)

(9/77)

Il O:her (Explain)

Exhibit 1 - Same Source

vunct no.

U50-0331

~

Unit _Duan7 'Arnald Energyj REFUELING INFORt1ATION Date June 14. 1982 Completed by Sidney Browni

~ Telephone 319-8E1_5611 1.

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for next refueling shutdown.

A.

September 7, 1982 3.

Scheduled date for restart following refueling.

A.

Unknown 4.

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

A.

Yes.

New'MAPLHGR tables will have to be included In Technical Specifications.

5.

Scheduled date(s) for submitting proposed licensing action and supportin.,} information.

{ A.

Unknown at this time..

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

6.

new or different fuel desigr ar supplier, unroviewed design or por-formance analysis methods, significant changes in' fuel design, new operating procedures.

A.

New fuel assemblies to be placed in the reactor will be more highly enriched than those currently in use.

5 The n'umbar of fuel assemblics (a) in the core and (b) in the spent 7.

fuel storage pool.

A.

a) 368 b),

448 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 l

9.

The projected date of the last refucling that can be discharged to the s;) cot fuel pool assuming the present licensed capacity.

A.

1998 G

9 7

Dock;t No. 050-0331 l

Unit Duane Arnold En rgy Cunt 1r Date Junr 14, L982 Complcted by S dney L. Brown Telephone 319-851-5611 i

NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 5-1 Normal plant operation at 445 MWe.

5-4 During normal operation while performing surveillance testing of the "B" i

RHRSW subsystem, "D" RHRSW pump discharge check valve V-46-11 was found to be leaking.

During operability testing of remaining RHRSW pumps, the "A" pump 1P-22A failed to reach the required discharge pressure.

R0 Report 82-32 5-7 Normal plant operation at 469 MWe.

5-9 Reactor scram at 0240 hours0.00278 days 0.0667 hours 3.968254e-4 weeks 9.132e-5 months due to loss of generator field.

5-10 Reactor critical at 2106 hours0.0244 days 0.585 hours 0.00348 weeks 8.01333e-4 months .

5-11 Main generator on-line at 0804 hours0.00931 days 0.223 hours 0.00133 weeks 3.05922e-4 months .

During normal operation subsequent to reactor startup, primary containment isolation valve, CV-4306, on the drywell and torus purge supply line failed to close completely.

R0 Report 82-033 5-13 Normal plant operation at 353 MWe.

5-16 Main generator off-line at 0909 hours0.0105 days 0.253 hours 0.0015 weeks 3.458745e-4 months .due to turbine trip.

Reactor scrammed due to high reactor pressure at 1123 hours0.013 days 0.312 hours 0.00186 weeks 4.273015e-4 months . Repair of emergency bearing oil pump initiated.

5-21 Reactor critical at 1802 hours0.0209 days 0.501 hours 0.00298 weeks 6.85661e-4 months .

5-22 Main generator on-line at 1805 hours0.0209 days 0.501 hours 0.00298 weeks 6.868025e-4 months .

5-23 Normal plant operation at 261 MWe.

5-25 During normal operation surveillance testing, RCIC pump did not deliver 400 gpm in auto flow control, and torus level high rise alarm was actuated.

R0 Reports Pending 5-26 Normal plant operation at 481 MWe.

5-31 Normal plant operation at 267 MWe.

I

Uccxet No, Ubu-UJJi Unit Donne ArnchLEn,ercy con Dat0 anne 14. 1982 U*E U Ud D7' bid"UY MAJOR SAFETY RELATED MAINTENANCE 50

. Telephone 319-851-E517 CATE SYSTEM COMPONENT DESCRIPTION 5-6-82 RHR Service Water "D" Pump Discharge Check. Valve V-46-11 Set screw and tack welds replaced.

5-6-82 RHR Service Water IP22A Pump Impellar. adjusted.

5-7-82 River Water Supply IP117C Pump Adjusted impellar.

5-10-82 RCIC M0-2400 Valve Replated. limit switch and reset torque.

5-11-82 Containment Atmosphere CV 4306 Valve Pneumatic valve cleaned, lubricated Control and reassembled.

I 5-17-82 Control Bldg. H&V "A" Chil.l er ' Conder.ser Cleaned tubes.

5-20-82 Turbine IP-40 Pump Replaced ' upper. bearing.

5-21-82 250 Volt DC Power 1D-40 Breaker Replaced. diode in current limiting device.

5-24-82 Containment Atmosphere "B" H.0 Monitor

]

Clea'ned gas, solenoid and checksd monitor.

2 2 Control 5-25-82 RCIC FIC-2509 Flow Control

Adjusted setting.

5-26-82 Drywell Radiation Monitors 1C-219-B Monitor Installed new filt.er.

5-26-82 RHR SW 1S-90B Strainer Cleaned and reinstalled screens.

8 nf

ML20054G215

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