ML20069E464

Monthly Operating Rept for Feb 1983

ML20069E464
Person / Time
Site:	Duane Arnold
Issue date:	03/15/1983
From:	Miller W IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20069E463	List: ML20069E461 ML20069E464
References
NUDOCS 8303220062
Download: ML20069E464 (6)

Text

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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 3-15-83 CCNPLETED BY William Miller TELEPH0tE 319-851-7238 OPERATING STATUS Notes

1. Unit Name Duane Arnold Enerqy Center

2. Reporting Period Fe br uary. 1983

3. Licensed Thermal Power (MWt): 1658

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

5. Design Electrical Rating (Net MWe): 538

6. Maximum Dependable Capacity (Gross MWe): 54 5

7. Maximum Dependable Capacity (Net MWe): 515 8.

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

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

10. Reasons For Restrictions, if Any:

This Month Yr-to-Date Cumu lat ive

11. Hours in Reporting Period 672.0 1416.0 70800.0

12. Number of Hours Reactor Was Critical 266.7 1010.7 51267.0

13. Reactor Reserve Shutdown Hours 0.0 0.0 0.0 14 Hours Generator On-Line 266.7 1010.7 49945.9

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated 04WH) 311704.8 1194016.8 61567456.0

17. Gross Electrical Erergy Generated (MWH) 105698.0 410045.0 20624 % 2.0

18. Net Electrical Energy Generated (MWH) 96462.4 380160.6 19294433.0

19. Unit Service Factor 39.7%

71.4%

70.5%

20. Unit AvalIabliIty Factor 39.7%

71.4%

70.5%

21. Unit Capacity Factor (Using MDC Net) 27.9%

52.1%

52.9%

22. Unit Capacity Factor (Uslog DER Net) 26.75 49.9%

50.7%

23. Unit Forced Outage Rate 0.0 0.0 17.5 24 Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Ref ueling commenced on February 11. 1983

25. If Shut Down At End Of Report Period Estimated Date of Startup: April 25,1983 Murbine Rating: 565.7 MWE Generator Rating: 663.5 (MVA) x.90 (Power Factor) = 597 MWe 8303220062 830315 PDR ADOCK 05000331 (9f77)

R PDR

4 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Energy Center '

DATE 3-15-83 COMPLETED BY William MIIler TELEPHONE 319-851-7238 MONTH Febr uary, 1983 DQY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Ne t)

(MWe-Net) 1 387 17 0

2 386 18 0

3 385 19 0

4 382 20 0

5 305 21 0

6 390 22 0

7 378 23 0

8 377 24 0

9 375 25 0

10 373 26 0

11 341 27 0

12 0

28 0

13 0

29 N /A 14 0

30 N /A 13 0

31 N /A 16 0

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

(9/77)

UNIT SHUTDOWNS AND POWER REDUCTIONS Docket No.

050-0331 Unit Name Duane Arnold Enercy Center Date 3-15-83 REPORT MONTH February, 1983 Completed by william Miller Tolophone 319-6>1-723d n

o

-,+

f%

Licenseo t

Cause & Corrective e-u 0

No.

Date

[

8 3

Event j,

En Action to

~

e R

2e Report #

1$

Prevent Recurrence s

L r o

om 2

>o ao 3 -

x 1

o mo ou O

O O

4 2/5/83 S

N/A B

N/A N/A N/A N/A Power reduction to reduce exposure to personnel conducting condenser leak testing 5

2/12/83 S

405.3 C

1 N/A N/A N/A Scheduled refueling (T h r u shutdown 2/28/83) 1 2

3 4

i F: Forced Reason:

Method:

Exhibit G-Instructions S: Scheduled A-Equipment Falluro(Explain) 1-Manual for Preparation of Data l

B-Maintenanco of Test 2-Manual Scrom.

Entry Sheets for Licensee 0-Refueling 3-Automatic Scram.

Event Report (LER) File (NUREv D-Rogulatory 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) x._..

Docket No. 055-0331' Unit Duane Arnold Energy Ctr i

Date 3-15-83 Completed by Wi l liam Mi l ler Telephone 319-851-7238 4

REFUELING INFORMATION 1.

Name of facility.

A.

Duane Arnold Energy Center i

2.

Scheduled date for next refueling shutdown.

A.

February 11, 1983 3.

. Scheduled date for restart following refueling.

A.

Apri l 25, 1983 J

i 4

Will ref ueling or resumption of operation thereafter require a technical specification change'or other license amendment?

Yes, the following outstanding changes will have to be included in the Technical Specifications:

A.

MAPLHGR Tables & MCPR Limits C.

Containment Load Case B.

Snubbers Avoldance 5.

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

A.

January 14, 1983 (RT S -147 )

C.

March 10, 1983 (RTS-146)

I B.

March 2, 1983 (RTS-140) 6.

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

new or different fuel design or supplier, un rev i ew ed design or performance analysis methods, significant changes in fuel design, new operating procedures.

l A.

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

4 1

7.

T he. number of fuel assemblies (a) In the core and (b) In the spent fuel storage pool.

A.

a) 368 b) 448 (status prior to ref ueling outage) 8.

The present licensed spent fuel pool storage capacity and the size of

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any increase in licensed storage capacity that has bee n requested or is planned, in number of fuel assemblies.

1 A.

2050 f

9.

The p r oj ect ed date of the last refueling that can be discharged to the

]

spent fuel pool assuming the present licensed capacity.

A.

1998 x

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Dockst No.

050-0331 Unit Duane Arnold Entrqy Center Deto 3-15-83 M i l l)e r MAJOR SAFETY RELATED MAINTENANCE C omp let ed by William Telephone 319-851-7238 DATE S Y ST EM COMPONENT DESCRIPTION 2/8/83 RCIC M O V -2 515 -MO full flow test valve Loose valve stem anti-rotation collar repair 2/11/83 MSIV-LCS Fuse Replaced fuse - r a n d om failure caused loss of MSlV-LCS "D"

leakage flow Instrumentation 2/11/83 RW Supply Flow Transmitter and Recorder Instrument callbration and baseline IST cause RW Supply pump to exceed ASM E developed head allowable 2/12/83 Reactor instrumentation Instrument Line Excess Flow Check Investigation continuing - Improper Valve valve position Indication 2/14-15/83 Various Safety Related Systems Snubbers Comprehensive inspection repair and and replacement of sn u b be r s (RO Report continuing pending) 2/21/83 ADS Pressure Switches on RHR for ADS Recalibration - Instrument drlft permissive in conservative d i r ect ion

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'4 Docket No. 055-0331 Unit Duane Arnold Enaray Ctr Date 3-15-83 Completed by William Miller Telephone 319-851-7238 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 1-83 Normal operation at 393 MWe.

2-5-83 Power reduction to 260 MWe to reduce personnel exposure during scheduled condenser leak testing.

2-8-83 RCIC declared Inop due to loose valve stem anti-rotation collar.

RO Report 83-004 4

River Water Supply System IP1178 and D pumps dec:ared Inoperable when 2-11-83 l

developed head exceeded ASME XI allowables.

Instrumentation recalibration required.

RO Report 83-005 2-11-83 MSIV LC S "D"

declared inoperative due to a blown fuse.

R0 Report 83-006 4

2-12-83 Reactor Instrumentation instrument Line Excess Flow check valve position problems.

R0 Report 83-007 e

2-12-83 Commence scheduled refueling shutdown.

i.

2-12-83 0239 Generator Breakers opened.

2-14-83 Uncontrolled release of 20 gallons of low level activity condensate service water.

ET S V Report 83-1.

2-21-83 During cold shutdown surveillance testing, RHR pressure switches for ADS found out of tolerance in conservative direction.

L RO Report 83-006 4

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