ML20070F669

Monthly Operating Rept for Nov 1982

ML20070F669
Person / Time
Site:	Duane Arnold
Issue date:	12/15/1982
From:	Watson M IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20070F668	List: ML20070F664 ML20070F669
References
NUDOCS 8212210210
Download: ML20070F669 (6)

Text

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"' s OPERATING DATA REPOP.T

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DOCKET NO. 050-0331-u DATE Decemoer75, 1982

. COMPLETED 1;Y fiarjt){als,on TELEPilONE 110 RR1-5611 -

OPERATING STATUS

1. Unit Name: Duano Arnold Enerav Center Notes

'2. Rep ~orting Period:

November 1982

3. Licensed Thermal Power (MWt):

1658

• 4. Nameplate Rating (Cross MWe):

565 (Turbine Ratina)

5. Design Electrical Rating (Net MWe):, 538

6. Maximum Dependable Capacity (Gror.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,if Any (Net MWe):

10. Reasons For Restrictions,if Any:

i O

This Month

. Yr.-to-Date Cumulative

!i. Hours In Reporting Period-720.0 8016.0_.

68640.0

12. Number Of Hours Reactor Was Critical 467.5 6033.fL.

49512.3

13. Reactor Reserva Shutdown Hours 0.0 _

0. 07 0.0-

14. Hour 2 Generator On-Line 452.5 580L.8 48191~.2

15. Unit Reserve Shutdown Hours u.U U.U 0.0

16. Gross Thermal Energy Generated (MWH) 573936 6268426.0 59321824.0 l

17. Gross Electrical Energy Generated (MWH) 193259 2081703.0 19856743.0

18. Net Electrical Energy Generated.(MWH) 178844 1946151.6 18577737.0

19. Unit Senice Factor 62.8 72.4

'70.2.

20. Unit Availability Factor 62.8 72.4 70.2 48.8 *

47. 1 52.6

21. Unit Capacity Factor (Using MDC Net)

22. Unis Cipacity Factor (Using DER Net) 46.7 45.1 50.3

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23. Unit Forced Outage Rate.

37.2 24.1 18.1-

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

First Quarter 1983 Refueling

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

• Turbine Rating:

565.7 MWe Generator Rating: 663.6 (MVA) x.90 (Power Factor) = 597 MWe 8212210210 821215 PDR ADOCK 05000331 R

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a AVERAGE DAILY UNIT POWER LEVEL

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DOCKET NO. 050-0331 _

Duane Arnoio UNIT rnarnv Center DATE December 15, 1988 COMPLETED BY Mark Watson l

1 TELEPHONE 319-851-5611 MONTII November, 1982 DAY AVERAGE DAILY POWEliLEVEL DAY

' AVERAGE DAILY POWER LEVEL (MWe. Net)

(MWe-Net) j 340 e

37 178 _

1 2

452 403 gg 3

19 411 4

317 507 20 294 417 5

6-6 522 77 7

.0' 523 23

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F-0 520 g

24 9

0 25 456 10 0

499 26

• II n ~

27 473-

-12 0

28 484 13 0

482 29 14 0

30 440 15 0

3, I6 0

INSTRIICTIONS On this foruatolist the average daily unit power level in MWe. Net for each day in the reporting nmnth. Compute to the nearest whole megawatt.

(9/77i t

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DOCKE1 NO. 050-0331 UNITSIIUTDOWNS AND POWER REDUCTIONS UNITNAME Duano Arnnlrl Fnergy Center DATE December 15. 1982 COMREED W Mad Watson REPORT MONTH Mnunmhnr 1982 TELEPl!ONE 319-851-5611' w

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$.E 3 Licensee

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Cause & Corrective

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.8 y 5 Event p

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No.

Date o.'

Action to 4

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.5 g; g Report.1 mo o

Prevent Recurrence u

o 18 11-3-82 F

O' d H

N/A N/A' N/A N/A Load reduction by load dispatcher 19 11-5-82 F

248

.A 4

A - Repair. Core Spray. Valve and j

other components 4-Manual S/D initiated, Manual scram used finally i

20 11-21-82 F

0.0 H

N/A N/A N/A N/A Load variation by load dispatcher

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2 3

4 I

F: Forced Reason:

Method:

Exhibit G. Instructions 3: Scheduled A Equipment Failure (Explain) 1 Manual for Preparation of Dats B Maintenance of Test 2-Manus 1 Scram.

Entry Sheets for Licensee i

C R.Tueling 3-Automatic Scram.

Event Repori(LER) File (NUREG.

I:

-l D Regulatory Restriction 4 Other(Explain) 016')

2' E Oscutor Training A License Exam!nstion i

l F-Administr::tive 5

8 i

C 0;wa:ional Errut (Explain)

Exhibit I.Same Sourec

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(9/77)

II 0:her (Explain) l

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Unit Duane Arnold Eneray Center l

D t3 U2cembar Ib, 1962 1

Completed by Mark Watson I

Telephone 319-851-5611 j

REFUELING INFORMATION I

1.

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for next refueling shutdown.

A.

Ist Quarter, 1983 3.

Scheduled date for restart following refueling.

A.

Unknown 4.

Will refueling or resumption of operation thereafter 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 supporting information.

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A.

Unknown at this time.

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i 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.

A.

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

7.

The number of fuel assemblies (a) in the core and (b) in the spent fuel storage pool.

A.

a)368 b) 448 l

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 5

9.

The projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

A.

3998

Occket No.

050-0331 Unit Duane Arnold Energy Cente Date December 15, 1982 Completed by Mark Watson Telephone 319 581-5611 MAJOR SAFETY REUATED MAINTENANCE f

Date System Component Description 11-3-82 Core Spray

'B' Core spray manual isolation valve, Inspected, adjusted limit switches ZS-2143 11-5-82 RHR RHR Fill Pump 1P-70 Rebuilt pump following trip on thermal overload 11-6-82 Con. Atmos. Cont.

PDIS 4305 Rx Bldg./ Torus Operator Recalibrated operator control' valve 11-7-82 Main Steam Head vents CV-4428, CV-4429 Repaired vent position indicatien 11-10-82 RHR Service Water RHR Service Water Pump 1P22A Reset impeller lift 11-13-82 RHR Service Water RHR Service Water Pump 1P22D Reset impeller lift l

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Dock t No, _050-0331 Unit Duane Arn ild Energy C nt r D te D cember 15, 1962 Complct d by Mark Watson i

i Telephone 319-8S1-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 11-1 Normal operation at 298 MWe.

11-1 During -nonnal operation, control rbd drive scram discharge volume (SDV) valves V-18-07, V-18-08, and V-18-6 were found in the proper position but not properly locked.

R0 Report 82-74

'l-3 Load reduction per load dispatcher.

11-5 Commenced shutdown to repair core spray valve handswitch ZS21438.

11-6 During shutdown drywell purge, PDIS-4305 opened drywell to suppression chamber vacuum breaker CV-4305 conservatively and would not reset to close CV-4305.

R0 Report 82-75 11-L During shutdown surveillance testing, drywell pressure switch PS-4310C tripped at 2.2 psig instead of the T.S. Table 3.2-8 required setpoint of 1.5

.5~psig increasing.

R0 Report 82-76 11-13 During shutdown surveillance testing, RHR service water pump 1P-22D failed the operability test by not attaining the technical specificatic a flow / head requirements.

R0 Report 82-77 11-16 Commenced reactor startup.

11-17 Reactor placed in Run Mode.

11-17 During normal operation surveillance testing, the pressure switch, PDIS 2139 channel 1, measuring the pressure difference between top of the cor.e support plate and inside the core spray sparger was found out of specification.

R0 Report 82-79 11-22 During normal operation, the 'B' river water supply system (RWSS) traveling screen wash pump, IP-112B, was found to have a discharge head of 33 psig instead of the required 60 psig.

R0 Report 82-80 11-23 During normal operation, the 'B' Standby Filter Unit heaters tripped on overtemperature.

R0 Report 82-81

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