ML20062L433
| ML20062L433 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 08/13/1982 |
| From: | Hill K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML20062L425 | List: |
| References | |
| NUDOCS 8208190109 | |
| Download: ML20062L433 (6) | |
Text
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s" OPERATING DATA REPORT DOCKET NO. 050-0331 DATE August 13, 1982 COMPLETED BY Kimuel L. Hill TELEPilONE 114 RG1 En11 t
OPERATING STATUS Notes Duane Arnold Eneray Center
- 1. Unit Name:
- 2. Rep'orting Period:.luly 14R2 1658
- 3. Licensed Thermal Power (MWt):
W (Turbinn Patind
- 4. Nameplate Rating (Gross 51We):
538
- 5. Design Electrical Rating (Net MWe):
545
- 6. Maximum Dependable Capacity ! Gross MWe):
515
- 7. Maximum 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. lf Any (Net MWe):
- 10. Reasons For Restrictions,if Any:
This Month Yr..to.Date Cumulative 744.0 5087.0 65711.0
- 11. Hours In Recortine Period 264.2 3405.5 46884.2
- 12. Number Of Iiours Reactor Was Critical 0.0 0.0' O.0
- 13. Reactor Reserve Shutdown Hours 138.1 3216.6 45606.0
- 14. Hours Generator On-Line 0.0 0.0 0.0
- 15. Unit Reserve 5;.utdown ilours 144367.2 4262220.4 57315618.4
- 16. Gross Thermal Energy Generated (MWil)
- 17. Gross Electrical Energy Generated (MWil) 45684.0__,
1438022.0 19213062.0 42334.1 1352342.2 17983927.5
- 18. Net Electrical Energy Generated (MWil) 18.6 63.2 69.4
- 19. Unit Senice Factor 18.6 63.2 69.4
- 20. Unit Availability Factor 11.0 51.6 53.1
- 21. Unit Capacity Factor (Using MDC Net) 10.6 49.4 50.9
- 22. Uni: Capacity Factor (Using' DER Net) 81.4 31.8 18.4
- 23. Unit Forced Outage Rate
- 24. Shutdowns Scheduled Oser Next 6 Months (Type. Date.and Duration of Eacht:
Dn fyol i n n, 1st annefor_ T 4 R't i
- 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 MWe b
8208190109 820813 (4/773 PDR ADOCK 05000331 l
R PDR
AVERAGE DAILY UNIT POWER LEVEL 050-0331 DOCKET NO.
/
Duane Arnold UNIT -Energy Center
/
DATE August 13, 1982
/
COMPLETED BY Kimuel L. Hill 319-851-5611 TELEPilONE MONT11 July 1982 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Net)
(MWe-Net) 0 37 0
1
~'
2 0
is 0
0 3
i9 0
0 4
20 0
5 21 0
0 6
22 0
7 23 0
0 8
24 9
0 0
25 0
10 26 153 I
II O
313 27 0
12 2g 364 0
13 29 333 0
14 30 340 0
is 3:
399 16 0
l INSTTtUCTIONS On this format list the average daily unit power lesel in MWe Net for each day in the reporting month. Compute to the nearest whole rnegawatt.
t l
(9/77 )
l
E g UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0331 UNIT NMIE Duane Arnold Energy Centel DATE August 13, 1982 REPORT MON HfJuly, 1982,-
COMPLETED BY Kirnuel L. Hill TELEPI:ONE 319-RR1 R611
.! ?
}
h Licensee P,
Cause 1 Correctise n
o No.
Date g
3g 2g$
Event gi g?
Action to
$E 5
j p; g Report a mO U
H Present Recurrence g
6 9
820602 F
605.9 A
1 82-034 CD C
Procedural violation on MISV opening sequence resulted in pressure transient that cracked two hydraulic speed control cylinders. Plant procedures and operating instructions were revised. Additional operator training was conducted.
10 820729 F
0.0 A:
N/A N/A CC E
Repair of steam leak 11 820730 F
0.0 A
N/A N/A CH E
Repair of steam leak 12 820731 F
0.0 H
N/A N/A N/A N/A Load reduction by load dispatcher I
2 3
4 F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A Equipment Failure (Explain) 1-Manual for Preparation of Data ll Maintenance ad Test 2 Manual Scram.
Ents) Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG.
D Regulatory Restriction 4-Other (Explain) 01611 F-Operator Training & License Examination F Administrative 5
G Operational Error (Explain)
Eshibit I - Same Source (9/77) 11 Other (Explain)
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Unit Duane Arnold Eneray Center
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Date August 13, 1982 REFUELIt!G INFORMATION Completed by Kimuel L. Hill
~
Tclephone 319-851-5611 1.
Name of facility.
A.,
Duane Arnold Energy Center 2.
Scheduled date for next refueling chutdown.
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 licence amendment?
A.
Y.es. New MAPLHGR tables will have to be included in Technical Specifications.
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 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 assemblies (a) in the core and (b) in the spent fuel storage pool.
l A.
a) 368 b) 448 I
S.
i 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 assemblics.
A.
2050 9.
The projected date of the Inst refueling that con be discharged to the spent fuel pool assuming the present licensed capacity.
A.
1998 e
9 4
+
Dock;t No. 050-0331 Unit Duan7 Arnold Entrgy C nt?r Data Auaust 13, 1982 Completed by Kimtfel L. Hill -
Telephone 319-851-5611 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE 7-1 Cold shutdown for MSIV repair.
7-6 During cold shutdown surveillance testing, high pressure turbine first stage pressure switches PS-1005A, C, and D tripped out-of-spec.
R0 Report 82-045 7-10 Cold shutdown continued.
7-18 MSIV repair completed. MSIVs local leak rate tested with satisfactory results.
7-19 During startup from a cold shutdown condition the "A" IRM did'not overlap the SRMs at 10E5 cps as required by IP01 Volume I section II.
R0 Report Pending During startup surveillance testing the "D" IRM indication range was found too low, and the "E" IRM was found inoperable downscale.
R0 Report Pending 7-20 During startup from a cold shutdown condition the "F" IRM was found inoperable downscale.
R0 Report Pending 7-24 Ten condenser tubes plugged.
7-26 Power operations resumed.
7-29 During normal operation surveillance testing the pressure differential switches which control reactor building to suppression chamber vacuum breakers CV-4304 and CV-4305 tripped out-of-spec.
R0 Report 82-047 7-29 Reactor power reduced to 30% for five hours for steam leak-repair.
7-30 During normal operation surveillance testing, 'C' main steam line high temperature indicating switch TIS-4445 tripped out-of-spec.
R0 Report 82-046 7-30 Reactor power reduced to 38% for four hours for steam leak, repair.
7-31 Reactor power reduced to 56% because of reduction in demand.
Dock;t No. 050-0331.
Unit Duane Arnold Energf < ente Date August 13, 1982 Completed by Kimuel L. Hill Telephone 319 581-5511 MAJOR SAFETY REEATED MAINTENANCE Date System Component Description 7-1-82 125 VDC Cell #16 of System #2 Cell replaced due to low voltage'.
7-1-82 Control Room Standby filter Unit 'B' Solenoid valve repaired. Air-modulating valve Habitability
~
replaced. Flow signal conditioning square-rooter repaired.
7-7-82 Containnent Drywell to Torus Vacuum Breakers Actuators rebuilt.
Atmospheric Dilution CV-4327A, B, C, E, G, H 7-12-82 RdR Service Water Heat exchanger IE-201B Drain line cleaned.
7-16-82 RHR Service Water Pumps IP-22A, IP-22C Adjusted impellers.
7-16-82 RHR Service Water
'A' and 'B' discharge check valves ~
Replaced hinge pin set screw and tack welded V-46-30, V-46-13 same in place.
7-18-82 Main Steam Isolation Valves MSIVs machined, lapped and local leak rate System tested satisfactory.
7-24-82 Main Condenser Tubes 10 tubes plugged.
S