ML20027B553

Monthly Operating Rept for Aug 1982

ML20027B553
Person / Time
Site:	Duane Arnold
Issue date:	09/15/1982
From:	Hill K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20027B549	List: ML20027B548 ML20027B553
References
NUDOCS 8209210238
Download: ML20027B553 (6)

Text

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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 9-15-82 COMPLETED BY K"muel Hill TELEPHONE 3' 9-851-5611 OPERATING STATUS

1. Unit Name: Duane Arnold Energy Center Notes

2. Reporting Eeriod: August 1982

3. Licensed Thermal Power (MWt): 1658

04. Nameplate Rating (Gross MWe): W (Titrhino Ratingl

5. Design Electrical Rating (Net MWe): 538

6. Maximum Dependable Capacity (Gross MWe): 545

7. Maximum Dependable Capacity (Net MWe): 51 5

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:

This Month Yr.-to-Date Cumulative

11. Hours in Reporting Period 744.0 5831.0 6645.0

12. Number Of Hours Reactor Was Critical 695.6 4101.1 47579.8

13. Reactor Reserve Shutdown Hours 0 0 0

14. Hours Generator On-Line 667.7 3884.3 46273.7

15. Unit Reserve Shutdown Hours 0 0 0

16. Gross Thermal Energy Generated (MWH) 573770.4 4835990.8 57889388.8

17. Gross Electrical Energy Generated (MWH) ** 181697.0 , , ,

1619719.0 19394759.0

18. Net Electrical Energy Generated (MWH) ** 168300.9 1520643.0 18152228.4

19. Unit Service Factor 89.7 ,

66.6 69.6

20. Unit Availability Factor 89.7 66.6 59.6

21. Unit Capacity Facwr (Using MDC Net) 43.9 50.6 53.0

22. Unit Capacity Factor (Using DER Net) 42.0 48.5 50.8

23. Unit Forced Outage Rate 10.3 28.9 18.3

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:

o Turbine Rating: 565.7 MWe Generator Rating: 663.5 (MVA) x .90 (Power Factor) = 597 MWe

• Includes 2 MWe correction from July 1982

("" "

8 2 0 9 21 o A,33

,0 AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 Juane A nold

nergybenter UNIT DATE 9-15-82 COMPLETED BY Kimuel Hill TELEPHONE 319-851-5611 1

MONm August 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) (MWe-Net) i 384 202 i7

~~

2 413 ig 247 3 421 19 237 4 468 :o 245 5 494 21 233 6 467 22 192 7 25 227 23 3 290 224 24 9 401 233 25 in 335 135 26 11 173 0 27 12 171 2 28 13 177 29 175 14 179 30 207 15 IO 31 211 1 16 223 i

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

(9/77 )

^

'B DOCKET NO. 050-0331 UNIT SHUTDOWNS AND POWER REDUCTIONS UNIT NAME Duane Arnold Energy Ctr s DATE 9-15-82 August 1982 COMPLETEDa t H REPORT MONTil _

n. .

- E E 3g 3 j .YIi Licensee ,E% l% Cause & Corrective No. Date g 3g i; js$ Event g? gO3 Action to H yI @ Ugg Report a mu g Prevent Recurrence 6

13 820807 F 19.3 H l N/A CC N/A Drywell and Condenser Bay Inspection 14 820810 F 0.0 H N/A N/A N/A N/A Load reduction by load dispatcher 15 820826 F 57.0 D 3 N/A CA N/A Reactor Scram from high level turbine trip I 2 3 4 F: Forced Reason: Method: Exhibit G -Instructions

- S: Scheduled A Equipment Failure (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 Training & License Examination F Administrative 5 G-Operational Error (Explain) Exhibit 1 - Same Source (9/77) Il-Other (Explain)

U0CKOL 60. UJU-UJJi Unit Duane Arnold Energy Center Date o_1g_g7 Completed by Kimuel Hill Telephone 319 581-5611 MAJOR SAFETY RELATED MAINTENANCE ,

Date System Component  ! Description 8/7/82 Primary Containment Airlock Local Leak Rate Tested 8/7/82 Reactor Protection Main steam isolation valve position Readjusted System switch 8/9/82 Reactor Vessel Instrument isolation valve Replaced Recirculation 8/11/82 CRD Hydraulic Discharge filter Replaced 8/13/82 River Water Supply River water makeup isolation valve Adjusted air pressure to operator CV-4915 8/17/82 RHR Service Water Pump 1P-22A Reset impeller 8/20/82 RHR Insulated piping attached to torus Pipe wall thickness checked 8/24/82 River Water Supply M0V-2903 Repacked

I l

Unit Duane Arnold Energy Ctr.

Date 9-15-82 .

l Completed by Kimuel Hill l

Telephone 319-851-5611 REFUELING INFORMATION

1. Name of facility.

A. Duane Arnold Energy Center

2. Scheduled date for next refueling shutdown.

A. 1st 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?

i 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.

A. Unkown at this time.

1

6. Important licensing considerations associated with refueling, e.g., new or different fuel design or supplier, unreviewed design or performance l 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.

l 7. The number of fuel assemblies (a) in the core and (b) in the spent i fuel storage pool.

1 A. a) 368 b) 448

8. The present licensed spent fuel pool storage capacity and the size of I 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 i spent fuel pool assuming the present licensed capacity.

A. 1998 l

, - Unit Duane Arnold Ennrgy Center Docket 050-0331 Date 9-15-82 Completed by Kimuel Hill Telephone 319-851-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 4

8-1 Normal operation at 384 MWe 8-7 Shutdown for Drywell and Condenser Bay inspection for leaks.

No leaks found.

8-8 Power increasing to 350 MWe.

8-9 During normal operation surveillance testing, reactor core isolation cooling steam line high pressure differential indicating switch tripped out-of-spec. R0 Report 82-51 During normal operation surveillance testing, drywell pressure switch PS-4312C tripped out-of-spec.

R0 Report 82-52 8-13 During normal operation, train 'A' of the river water supply steam was found to be inoperable when CV-4915 failed to open.

R0 Report 82-53 i

8-15 During normal operation surveillance testing RHR service water pump 1 1P-22A failed to provide rated pressue at rated flow.

1 R0 Report 82-54 4

8-18 During normal operation torus level recorder LR-4384 drifted down and remained at a new lower level.

R0 Report Pending t

8-23 Normal operation at 230 MWe.

l 8-26 Reactor scram on turbine trip from high water level during surveillance testing.

4 8-28 Startup from scram of 8-26.

8-31 Normal operation at 210 MWe.

l

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