ML20065A706

Monthly Operating Rept for Jan 1983

ML20065A706
Person / Time
Site:	Duane Arnold
Issue date:	02/19/1983
From:	Watson R IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20065A684	List: ML20065A681 ML20065A706
References
NUDOCS 8302220134
Download: ML20065A706 (6)

Text

OPERATING DATA REPORT g

i DOCHET NO. 050-0331 DATE 2-14-83:

CCNPLETED BY Mark Watson TELEPHONE 319-851-7611 OPERATING STATUS Notes

1. Uni t Name Duane Arnold Eneray Center

2. Reporting Period January, 1983 I

3. Licensed Thermal Power (MWt):

1658

1. 4.' Nameplate Rating '(Gross MWe):

565 (Turbine Ratina)

5. Design Electrical Rating (Not MWe): 538

6. Maximum Dependable Capacity (Gross MWe): 545

7. Maximum Dependable Capacity (Not MWe):

515

8. If Changes Occur in Capacity Ratings (items Number 3 Through 7) Since tne 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' Cumu lat ive

11. Hours in Reporting Period 744.0 744.0 70128.0

12. Number of Hours Reactor Was Critical 744.0 744.0 51000.3 0.0 0.0 0.0

13. Reactor Reserve Shutdown Hours

14. Hours Generator On-Line 744.0 744.0-49679.2

15. Unit Reserve Shutdown Hours.

0.0 0.0 0.0 -

16. Gross Thermal Energy Generated (MWH) 886231.2 886231.2 61255751.2

17. Gross' Electrical Energy Generated (MWH) 304347.0 304347.0

'20519264.0

18. Net Electrical Energy Generated (MWH) 283698.2 283698.2 19197970.6

19. Unit Service Factor _

100.05 100.05 70.8%

20. Unit Availability Factor 100.05 100.05 70.8%

21. Unit Capacity Factor (Using MDC Net) 74.05 74.05 53.25

22. Unit Capact ty Factor (Using DER Net) 70.95 70.95 50.9%

23. Unit Forced Outage Rate 0.0 0.0 17.65

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

Refuelina, February 11, 1983 8 weeks

)

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

4

. Turbine Rating: 565.7 MWe Generator Rating: 663.5 (MVA) x.90 (Power Factor) = 597 MWe (9/77) 8302220134 830214 PDR ADOCK 05000331 R

PDR

4 4

AVERAGE DAILY UNIT POWER LEVEL' DOCKET NO. 050-0331 UNIT Duane Arnold Eneroy Center DATE 2-14-83 COMPLETED BY Mark Watson TELEPHONE 319-851-7611 M) NTH January; 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 468 17 415 2

478 18 432 3

478 19 433 4

475 20 431 5

474 21 422 6

470 22 296 7

455 23 302 8

273 24 414 9

333 25 428 10 372 26 411 11 435 27 378 12 444 28 426 13 439 29 420 14 436 30 422 15 301 31 420 16 300 4

l b6TRUCT10NS

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

1 (9/77)

UNIT SHUTD0tNS AND POWER REDUCTIONS Dsc kr,t Ns.

050-0331 Unit Nsco Dusno Arnold E n r.rg y Centr!r Dato 2-14-83 REPORT MONTH January, 1983 Completed by Mark Wa t so n Telephone 319-851-7611 n

L

-a0 Licensee Cause & Corrective eo n

e e

. [

37$

Event

$n Action to

~

No.

Date S

E s$c Report #

' Prevent Recurrence o

L m e

oa z

>. o e o sw g

Z O

mo oO o

o O

1-7,83 F

N/A B

N/A N/A N/A N/A Power reduction to perform 1

+

STP 43 COO 1 and STP 43A002

" Scram Insertion time test" 2

1-14-83 F

N/A H

N/A N/A N/A N/A Load reduction by load dispatcher 3

1-21-83 F

N/A H

N/A N/A.,

N/A N/A Load reduction by lodd d i s pa tch er 4

1 2

3 4

F: Forced Reason:

Method:

Exhib.it G-In struct i ons S: Scheduled A-Eauipment Failur6(Explain) 1-Manual for Preparation of Data B-Maintenance of 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 Trainin'g & License Examination F-Administrative 5

Ex h l'b i t 1-Same Source G-Opera,tional Error (Explain)

(9/77)

,'e H-Oth e r ( Ex p l a i n )

t w

-_%e 4-e = = ear - W M JC

4 Docket No. 055-0331 Unit Dumnm Arnold Enrray Ctr j

Date 2-14-83 Completed by Mark watson Telephone 319-851-7611 REFUELING INFORMATION 1

Name of facility.

A.

Duane Arnold Energy Center 2

Scheduled date for next refueling shutdown.

A.

February 11, 1983 3

Scheduled date for restart following refueling.

A.

April 9,

1983 (Preliminary) 4 Will ref ueling or resumption of operation thereafter r eq u l r e a t ech r. I ca l specification change cr other license amendment?

Yes, the following changes will have to be included In the Techn ica l Specifications:

A.

MAPLHGR Tables C.

Torus Dralned Ref ueling Operat ions B.

MCPR Table D.

Common Reference Level 5

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

A.

January 14, 1983 C.

December 6, 1982 (RTS-146)

B.

January 14, 1983 D.

December 13, 1982 (RTS-141) 6 Important licensing considerations associated with r ef ue li ng, e.g, new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

A.

N ew fuel assemblies to be placed in the reactor will be more 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 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 date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

A.

1998

[

Dnckot N a, 050-0331 Unit Durn, Arnnid Encray Ctcr Dote 2-14-8 3 MAJOR SAFETY RELATED MAINTENANCE Comp let ed by Mark Watson Telephone 319-851-7611 DATE SYSTEM COMPONENT DESCRIPTION 1-4-83 Reactor Core isolation Governor Valve Flanges Replaced old F le xa t al l i c, torq ued unit Cooling (RCIC) flange per spec.

1-25-83 Primary Containment H and V IK-18A Drywell P compressor R eca l i br a t ed per spec.

controller 1-25-83 Reactor Protectir System (RPS)

RPS low water level indicating R eca l i bra t ed per STP.

l switch LIS-4592A

e Docket No. 055-0331 Unit Duenn Arnold Eneroy Ctr s'

Da te 2-14-8 3 Completed by Mark Watson lelephone 319-851-7611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE l-1-83 Normal operation at 483 MWo.

1-4-03 During normal operation surveillance testing, steam was discovered escaping from HV-2406, the RCIC turbine hy drau lic goverfor valve.

The RCIC steam isolation valves MO-2400 and MO-2401 were closed to commence repairs, rendering the RCIC system Inoperable.

RO Reprt 83-01 1-7-83 Power reduction to perf orm STP 43C001 and STP 43A002 " Scram insertion Time Test".

1-14-83 Load reduction per load dispatcher.

1-21-83 Load reduction per load dispatcher.

1-24-83 During normal operation, the "drywell to torus low differential pressure" alarm was recolved.

RO Report 83-02 1-25-83 During normal operation surveillance testing, LIS-4592A (one of four Reactor Protection System Low Reactor Water Level Indicating Switches) tripped out of specification:

R0 Report 83-03 J