ML20052G556

Monthly Operating Rept for Apr 1982

ML20052G556
Person / Time
Site:	Duane Arnold
Issue date:	05/14/1982
From:	Brown S IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20052G551	List: ML20052G550 ML20052G556
References
NUDOCS 8205180459
Download: ML20052G556 (7)

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OPER ATING 14ATA RFM"T

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r)OCKEENO. _050-0331 DATE May 14, 1982 COMPI.ETED BY _Sidne_y L. Brown TELEPl!ONr. 3.19-851-5611 OPERATING STATUS

1. Unit Name: Duane Arnold Enerqy Cente,.

Notes

2. Rep'orting Period:

April, 1982 1658

3. Licensed Thermal Power (MWt).

• 4. Nameplate Rating (Gross MWe): ' 565 (Turbine Ratina) 538

5. Design Electrical Rating (Net MWe):

6. Maximum Dependab!c Capacity (Gro:.s MWe):

545 515

7. Maximum Dependable Capacity (Net MWe):

8. If Changs 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 Restsictions,If Any:

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' This Month

. Yr.-to.Date Cumulative

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I1. Ilours in Reporting Period' 719 2,879 63,503

12. Number OfIlours Reactor Was Critical 359.9 2,519.9 45,998.6

13. Reactor Reserve Shutdown llours 0

0-0-

336.4 2,496.4 44,885.8

'14. IIcurs Generator On Line

15. Unit Reserve Shutdown flours 0

0 0

16. Gross The mal Energy Generated (MWil) 338,008.8 3,442,034.8 56,495,432.8

17. Gross Electrica! Energy Generated (MWil) 113.608 ___.

1,163,591

_ 18,938,631

18. Net Electrical Energy Generated (MWil) 106.834.5 1,097,251.4 17,728,836.8

19. Unit Service Factor 46.8 86.7 70.7_

20. Unit Availability Factor 46.8 86.7 70.7

21. Unit Capacity Factor (Using MDC Net) 28.9

• 74.0 54.2

22. Unit Capacity Factor (Using DER Net) 27.6 70.8 51.9

23. Unit Forced Outage R.-:e 4

.6 16.4

24. Shutdowns Scheduled Over Next 6 Months (Typc. Date.and Duration of Eachi:

Refueling, September 7, 1982, 8 weeks

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

• Turbine Rating:

565.7 MWe Generator Rating:

663.5 (MVA) x.90 (Power Factor) = 597 MWa 8205180459 l

. (n/773

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AVERAGE DAILY UNITPOWER LEVEL DOCKETNO. _050-0331 Duane Arnold UNIT _Eneray Center DATE May 14, 1982 COMPLETED BY Sidney L. Brown TELEPilONE _319-851-56il MONTil April 1982 DAY AVERAGE DAILY POWER' LEVEL DAY (MWe Net)

AVERAGE DAILY POWER LEVEL (ywe. Net)

I 269 17 0

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2 251 18 37 3

4 39 p44 4

0 20 249 5

0 21 747 6

0' 22 254 7

0 23 239 W

8 0

24 R4 9

0 25 312 to 0

26 427

' II O

27 454 12 0

28 443 13 0

29 445 14 0

30 466 15 0

33 16 n

INSTRUCTIONS On this fonnat.hst the average daily unit p.iwer levelin MWe Net for each day in the reporting the nearest whole rnegawatt.

(81/771 w

+

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7 g c-

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DO i. O5 UNIT SilUTDOWNS AND POWER REDUCTIONS rno6a t.nergy Ctr.,

t Du e DATE Mav 14 1962 COMPLETED BY Sidney L Brown REPORT MONT11 Aor11 1982 TELEPl!ONE 319-851-5611 Licensee

,E s Cause & Corrective

.] ?

1 Yh o "'g.

3 Action to i

No.

Date g

3g

.8 s s Event p

g Prevent Recurrence H

gE s

Ji;g g Report :

mU ou ga e

5 820401 S

419 B

1 Shutdown of the reactor for the April maintenance cutage 6

820423 l'

14 A

3 Loose connection in the metering i

circuit'of the auxiliary transformer,i Block replaced and reconnected.

i i

1 I

2 3

4 F: Forced Reason:

Metho6:

Exhibit G. Instructions S: Scheduled A Eetuipment Failure (Explain) 1-Manual for Preparation of D::ta D Maintenance of Test 2 M:nual Scram.

Entry Sheets for Licensee C Refueling 3 Automatic Scrum.

Event Report (LER) File (NUREG.

D-Regulatory Restriction 4 Other(Explain) 0161)

!? Opentor Training & License Examination F Adr nistrative S

G Ope-r.iunal Err r (E. elain)

Exhibit 1. Same Source (9/77) 11 O:her (Exp!ain)

E-Unit Danne

[]f JIEftlELING JNfCRl!ATION May_J. Q 182 Completed by Sidney B,rown

' Telephone 3197,1 !,ci1 8

1.

t!ame of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for next refueling shutdoun.

A.

September 7, 1982 3.

Scheduled date for restart follouire refueling.

A.

Unknown 4.

11111 refueling or resumption of operation thercarter require a technical specification change or other license amendment?

A.

Yes.

New MAPtHGR tables will have to be. included in Technical Spdcifications.

t 5.

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 peri formance analysis methods, significant changes in' fuel design, new operatang 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 assemblien (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 si7c-of any increase in licensed storage capacity that has been requested

-or is planned, in number of fuel assemblies.

A.

2050 9.

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

A.

1998

Cocket HC.

C50-0331 Ur.itg y,a w emggcer -

Date Nav 14, 1930 T

MAJOR SAFETY RELATED MAINTENANCE gp g

DATE SYSTEM COM?CGENT DESCRIPT!C" 4-2-82 River Water Supply IP-117A Pump Removed debris and reset 4-6-82 Control Building H&V IV-AD-31A Dampers Replaced actuator 4-8-82 RHR GBS-16-H107 Variable Spring Support Verified setting 4-8-82 RHR Pipe in spool GBB-4-b Dent filled 4-10-82 Standby Diesel Generators 1G-31 Diesel Generator Repaired stud on vertical drive inspection cover 4-12-82 Standby Diesel Generator IG-31 Diesel Generator Replaced springs on pilot and start solenoids 4-14-82 RHR IP-70 Minimum Flow Line Replaced section of pipe 4-14-82 RHR CV-2033 Valve Ground out indication of weld crack

'4-15-82 Emergency Service Water HBD-24-H-158 Hanger Base Installed missing anchor bolt 4-16-82 Standby Diesel Generator 1G-31 Diesel Generator Replaced air start solenoid 4-16-82 Main Steam Isolation SRV-4406 Tail Pipe Replaced hangers 4-17-82 RHR M0-2004 Valve Power Supply Replaced transfonner 4-17-82 RHR Cooling Water IP-22B Pump Straightened shaft 4-18-82 RHR 1P-70 Pump Installed new impleller 4-22-82 Rive.c Water Supply 1P-117A Pump Adjusted clearance 4-23-82 RHR GBB-16-H105 Variable Spr,ing Support Verified setting 4-27-82 Containment Atmosphere

.tP-29A Sample Pump Changed pumps Control 4-27-82 Containment Atmosphere RE-8101A Monitor Dried out detector and checked [

Control i

J

Docket flo. 050-0331 Unit Duane 7Fnold Energy Center Da te l ay_14,_198P j

Completed by Sidney L. Brown Telephone 319-85_1-5611_

f1ARRATIVE

SUMMARY

OF OPERATIt'G EXPERIEl;CE 4-1 Plant shutdown underway for maintenance outage, power at 294 MWe.

4-3 The main generator was taken off-line at 0226 hours0.00262 days <br />0.0628 hours <br />3.736772e-4 weeks <br />8.5993e-5 months <br />.

The reactor was subcritical and taken out of the Run mode at 0356 hours0.00412 days <br />0.0989 hours <br />5.886243e-4 weeks <br />1.35458e-4 months <br />.

4-4 During cold shutdown while performing surveillance testing, suppression chamber to drywell vacuum breaker valve, CV-4327D, failed to close completely.

R0 Report 82-025 4-7 During cold shutdown while performing surveillance testing of the main steam isolation valve leakage control system (MSIV-LCS), main steam line pressure switch PS-8404C failed, rendering the MSIV-LCS on the "C"

main steam line inoperable.

R0 Report 82-026 4-10 During cold shutdown while removing pipe insulation to access the RHR fill line valves for maintenance, external corrosion was found on RHR fill pump 1P-70 minimum flow line (1"-GBB-26).

R0 Report 82-28 4-11 During cold shutdown surveillance testing, drywell pressure switches PS-4310C and 4312C tripped out-of-spec at 2.35 and 2.45 psig, respectively.

R0 Report 82-27 4-17 Reactor was critical at 1809 hours0.0209 days <br />0.503 hours <br />0.00299 weeks <br />6.883245e-4 months <br />.

4-18 Main generator on-line at 1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br /> wi.th a load of 10 NWe.

4-19 During normal operation, the valve M0-8401D was not indicating its position in the control room and could not be operated from the control room.

Ro Report 82-29 4-20 The plant power level was 259 MWe.

4-21 During normal operation while performing surveillance testing, the HPCI steam supply pressure switch, PS-2246A, setpoint was out-of-spec at 110 psig.

R0 Report 82-30 A

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Docket llo.. 050-0331 l

Unit Duane 7.rnold Lnergyy Center 1

Datel9yli 1982 Completed by Sidney L. Brown Telephone 3j9-851-5611 f1ARRATIVE SUWARY OF OPERATII;G EXPERIEf1CE 4-23 Reactor scrammed at 2203 hours0.0255 days <br />0.612 hours <br />0.00364 weeks <br />8.382415e-4 months <br /> due to a loose connection in the auxiliary transformer 6.:etering circuit.

4-24 The reactor was critical at 0658 hours0.00762 days <br />0.183 hours <br />0.00109 weeks <br />2.50369e-4 months <br />. The main generator was on-line at 1204 hours0.0139 days <br />0.334 hours <br />0.00199 weeks <br />4.58122e-4 months <br />.

4-26 During normal operation,the control rod accumulator,10-07, was declared inoperable due to a leaking nitrogen charging valve.

R0 Report Pending 4-26 During normal operation surveillance testing, pressure differential switch, PDS 4304, tripped out-of-spec at.7 and.9 psi.

Ro Report Pending 4-30 flormal plant operation at 503 MWe.

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