ML20032D877

Monthly Operating Rept for Oct 1981

ML20032D877
Person / Time
Site:	Duane Arnold
Issue date:	11/13/1981
From:	Van Sickel J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20032D872	List: ML20032D871 ML20032D877
References
NUDOCS 8111180215
Download: ML20032D877 (7)

Text

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- -..e OPERATING DATA REPORT DOCKET NO. 050-0331

~

DATE November COMPLETED BY J. Van St..ckel TELEPIIONE 114 RG14611 -

OPERATING STATUS

1. Unit Name:

Ouane Arnold Eneroy.C nter Notes

2. Re;iorting Period:

Octqber. 1981 3658

3. Licenad Thermal Power (MWt):

• 4. Nameplate Rating (Gross MWe): %6G (Turhino Rating)

5. Design Electrical Rating (Net MW.r):

538 545

6. Mai. ?um Dependable Capacity (Gross MWe):

515

7. Manimum Dependable Capacity (Net MWe):

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 II. Hours in Reporting Period 745 7 J46 54.160

12. Number Of Hours Reactor Was Critical 173.5 4.861.5 42.030.2

13. Reactor Reserve Shutdown Hours 0

0 0

'14. Hours Generator On.Line 137.7 4,680.6 40,957.6

15. Unit Reserve Shutdown Hours 0

0 0

16. Gross Thermal Energy Generated (MWH) 84.761 5.810,269 51,808,907

17. Gross Electrical Energy Generated (MWH) 28.228 1.963.724 17.366.411

18. Net Electrical Energy Generated.(MWH) 25.637 1,839,732 16.251,770

19. Unit Service Factor 18.5%

64.2%

69.2%

20. Unit Avzilability Factor 18.5%

64.2%

69.2%

21. Unit Capacity Factor (Using MDC Net) 53.3%

6.7%

49.0%

22. Unit Capacity Factor (Using DER Net) 6.4%

46.9%

51.1%

0.0%

4.6%

17.6%

23. Unit Forced Outage Rate

24. Shutdowns Scheduled Over Next 6 Months (Type, D.are,and Duration of Each1:

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

• Turbine Rating:

565.7 MWe Generator Rating:

663.5 (MVA) x.90 (Power Factor) = 597 MWe 8111180215 811113 PDR ADOCK 05000331 R

PDR P/77)

o

..y AVERAGE DAILY UNIT POWER LEVEL DOCKE1 NO. 050-0331 UNIT Duane Arnold Energy -

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DATE November COMPLETED BY J. Van Sickel 319-851-5611 TELEPilONE MONTil October, 1981 DAY AVERAGE I

PO VER' LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) 209 0

I 17 2

221 18 n

3 211 19 0

4 20 0

5

- 0 0

21 22 O

0 7

g 0

0 g

24 9

0 25 0

10 0

26 0

11 0

27 0

0 0

12 28 0

0 13 29 0

34 30 120 0

201 15 3

0 16 INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/771

4 s

e UNITS!!UTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0331 UNIT NAME Duane Arnold Energy Centes DATE November COMPLETED BY

.1. Van si cicol REPORT MONT1f October, 1981 TELEPilONE 319-851-5611

.! E

}

.5g Licensee

,En,

t Cause & Corrective No.

Date g-3g y

,g g s Event g?

o-1 Action to H

$E 5

Ji @ =

Report

• mO-

!O Prevent Recurrence'

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u e

f I

i l

21, 811004 S

607.3 D,A 1

The reactor was shutdown as scheduled to inspect a weld in the recirculation system to satisfy an NRC requirement.

Startup was delayed by repairs which had to be'made to the reactor water cleanup system and to the feedwater j

check valves.

l 1

i l

2 3

4 F: Forced Reason:

Method:

Exhibit G Instructions S: Scheduled A. Equipment Failure (Explain)

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

Entry Sheeis for Licensee t

C Refueling 3-Automatic Scram.

Event Report (LER) File (NUREG-I i

D Regulatory Restriction 4-Other (Explain) 0161) l E Operator Training & License Examination F Administrztive S

l G. Operational Error (Explain)

Exhibit I - Same Source (9/77) 11-Oiher (Explain) 1

vocnet no.

050-0331

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Unit Duane Arnold Energy fent Date Hoyember IlEfUELING Ii\\'f0m1ATION Completed by __J. Van Sickel Telephone 319-851-5611 1.

Name of facility.

A.

Du.ane Arnold Energy Center 2.

Scheduled date for next refueling shutdown.

A.

Fall, 1982 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 MAPL'iGR tables will have to be included in Technical Specifications.

S.

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

' A.

Unknown at this time.

6.

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

new or different fuel design or supplier, unreviewed design or per-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.

7.

The number of fuel assemblics (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

Docket No.

050-0331 Unit Duane Arnold Enerav centet Date November hU MAJOR SAFETY RELATED MAINTENANCE e p on 319-561 c

DATE SYSTEM COMPONENT DESCRIPTION 10-1-81 Reactor Protection "A" RPS M-G Set Replaced undervoltage relay 10-8-81 RHR MOV-1900 Replaced limit and torque switches 10-8-81 Reactor Vessel CV-4639 Replaced limit switches Recirculation 10-23-81 Containment Atmospheric TE-4328A Replaced RTD Control 10-24-81 Core Spray MOV-2100 Rewound motor 10-25-81 Main Steam Isolations PT-8404C Installed new amplifier card and ADS 10-26-81 HPCI DT-2209 Replaced trap internals 10-27-81 Feedwater V-14-1 and V-14-3 Replaced feedwater check valve-seal rings 10-31-81 Containment Atmospheric AN-8181A Installed new chemicals Control r

Docket No. 050-0331 finit Duane Arnold Energy Center Date November a

Completed by J. Van Sickel Telephone 319-851-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 10-1 At the beginning of the report period the plant was operating at 245 MWe.

The plant was operating at reduced power levels due to lack of system demand.

10-4 A reactor shutdown began at 0849. The purpose of the shutdown was to perform maintenance and to allow for inspection of a weld on the recirculation system piping.

The generator was removed from the line at 1251 hours0.0145 days <br />0.348 hours <br />0.00207 weeks <br />4.760055e-4 months <br />. All control rods were inserted by 1935 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.362675e-4 months <br />. Both recirculation pumps were secured at 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br />.

The reactor was in cold shutcown at 2248 hours0.026 days <br />0.624 hours <br />0.00372 weeks <br />8.55364e-4 months <br />.

10-12 The reactor water cleanup system was isolated and drained to allow replacement of a piping section.

10-17 Repairs to the reactor water cleanup system were completed.

10-18 During a valve line up check, "D" main steam line MSIV leakage control system manual valve V-84-16 was found closed.

R0 Report 81-037 10-18 Plant startup was delayed due to unanticipated NDT requirements being placed on welds made as part of the new post accident sampling system installation.

10-21 An additional delay to plant startup was encountered when it was found the bonnet seals on both feedwater check valves were leaking and would require replacement.

10-26 Preparation for plant startup was begun. The reactor was critical at 0254 hours0.00294 days <br />0.0706 hours <br />4.199735e-4 weeks <br />9.6647e-5 months <br />. A leak was found at the pilot flange of main steam relief valve PSV 4407 and a reactor shutdown was begun. All control rods were fully inserted by 1937 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.370285e-4 months <br />.

The reactor was in cold shutdown at 2241 hours0.0259 days <br />0.623 hours <br />0.00371 weeks <br />8.527005e-4 months <br />.

10-28 An Emergency Preparedness exercise was conducted which involved the Control Room, Technical Support Center, Operations Support Center, Emergency Operations Facility, Local, County, State and Federal Government Agencies.

Following the drill, preparations for plant startup were begun. The reactor was critical at 2129 hours0.0246 days <br />0.591 hours <br />0.00352 weeks <br />8.100845e-4 months <br />.

Docket No. 050-0331 Unit Duane Arnold Energy Center Date November Completed by J. Van Sickel felephone 319-851-5611 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 10-29 Problems were experienced controlling level with the "A" feedwater regulating valve. The "B" feedpump and "B" reg valve were placed in service and plant startup continued.

The main generator was placed on the line at 2012 hours0.0233 days <br />0.559 hours <br />0.00333 weeks <br />7.65566e-4 months <br /> and a power increase begun.

10-30 A plant shutdown was begun when it became apparent the containment would not be inerted to less than 4% within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of placing the mode switch in RUN.

R0 Report Pending The shutdown was terminated at 2130 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.10465e-4 months <br /> when the containment oxygen concentration was reduced to less than 4%.

A power increase was begun at 2222 hours0.0257 days <br />0.617 hours <br />0.00367 weeks <br />8.45471e-4 months <br />.

10-31 The plant was operating at 242 MWe.