ML20040A217
| ML20040A217 | |
| Person / Time | |
|---|---|
| Site: | Duane Arnold  |
| Issue date: | 01/15/1982 |
| From: | Van Sickel J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT |
| To: | |
| Shared Package | |
| ML20040A216 | List: |
| References | |
| NUDOCS 8201200554 | |
| Download: ML20040A217 (7) | |
Text
OPERATING DAT A R El' ORT DOCKET NO. 050-0331 DATE January 1]i,1982 COMPLETED fly 6_ Van,,Sickel i
TELEPIIONI: 314-RG1 8ifill OPERATING STATUS I. Unit Name:
Duane Arnold Energy Center Notes
- 2. Regiorting Period:
December, 1981
- 3. Licensed Thermal Pow er (MWr):
1658
- 4. Nameplate Rating (Cross MWe):
'G6E (T"rhinn Pafinn)
- 5. Design Electrical Rating (Net MWe):
8i3R
- 6. Maximum Dependable Capacity (Gross MWe):
545
- 7. Maximum Dependable Capacity (Net MWe):
515
- 8. If Changes Occur it. 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
- 11. Hours in Reporting Period 744 8,760 60,624
- 12. Number Of flours Reactor Was Critical 728.5 6,310 43,478.7
- 13. Rehetof Reserve Shutdown Hours 0
0' 0
'I4. Hours Generator On Line 711.8 6,112.4 42,389.4
- 15. Unit Reserve Shutdown Hours 0
0 0
- 16. Gross Thermal Energy Generated (MWH) 553,130 7,054,760 53,053,398
- 17. Gross Electrical Energy Generated (MWH) 180.377 2.372.353 17.775,040
- 18. Net Electrical Energy Generated.(MWil) 167,929 2,219,548 16,631,585
- 19. Unit Service Factor 95.7%
69.8%
69.9%
- 20. Unit Availability Factor 95.7%
69.8%
69.9%
43.82 49.2%
53.3A
- 21. Unit Capacity Factor (Using MDC Net)
- 22. Unit Capacity Factor (Using DER Net) 42.0%
47.1%
51.0%
- 23. Unit Forced Outage Rate 4.3%
4.1%
17.1%
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- 24. Shutdowns Scheduled Over Next 6 Months (Type.Date.and Duration of Eacht:
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- 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 8201200554 820115 PDR ADOCK 05000331 R
PDR (9p71
AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0171 Uuane Arnoic UNIT Enorav Center DATE January 15, 1982
~~
COMPLETED BY J. Van Sickel TELEPHONE 319-851-5611 MONT11 December, 1981
^
DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe Ne )
(MWe-Net) 1 256 281 37
~
2 258 244 33 3
272 39 17 4
257 20 133 5
- 212 258 21 6
44 226 22 7
113 233 23 8
250 24 234 9
252 217 25 10 796 ~
26 220
'11 257 222.
27 12 258 224 73 13 259 29 223 14 316 223 30 281 20 15 33 16 254 INSTRUCTIONS On this format, list the average daily unit power levelin MWe Net for each day in the reporting month the nearest whole megawatt.
(9/77) e
UNITSilUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0331 UNIT NAME Ouane Arnold Energy C DATE January 15. 1982 COMPLETED BY 1-Van sirkol REPORTMONT1f December.1981 TELEPilONE 114 R91 9611 w,
's, E 5"
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Licensee E*
2 _e s-je.s X Cause & Corrective c8'.
No.
Date g.
pg g5 Event u7 g
Action to
$E 5
j di j Report *
<# u ju Prevent Recurrence S
f 22.
811205 F
9.9 8
3 The reactor scrammed during turbine control valve testin~g.
23.
811219 F
22.3 A
1 Reactor was shutdown to allow repairs to be made to the "B" reactor feed pump seal water return line.
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F: Forced Reason:
Method:
Exhibit G Instructions S: Scheduled A-Equipment Failure (Explain)
- 1. Manual for Preparation of Data B Maintenance or Test 2-Manual Scram.
Entry Sheets for Licensee C Refueling 3 Automatic Scram.
Event Report (LER) File (NUREG-D-Regutatory Restrictton 4-01her (Explain) 0161)
E-Operator Training & Ucense Examination F-Admmistrative 5
G Operational Error (Explain)
Exhibit I Same Source (9/77)
Il Other (Explain)
REFUEllNC INFORf1AT10N Date January. 15, 1982 Completed by _J. Van Sic
' Telephone 319-851-! KIT ~
1.
Name of facility.
A.
uuane Arnold Energy Center 2.
Scheduled dale for next refueling shutdown.
A.' September 4, 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 amend, ment?
A.
Yes. New NAPLHGR tables will have to be included in Technical Spec'ifications.
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.
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 assu:ning the present licensed capacity.
A.
1998 s
&%%iWndvo N
Unit Dyann Arnold E ag t
Date January 15, 1982 Completed by J. Van Sice MAJOR SAFETV RELATED MAINTENANCE Telephone -319-851-5611 DATE SYSTEl4 COMPONENT DESCRIPTION 12-5-81 Control Building H&V 1V-AD-31A Installed new bearings and shaft in damper operator.
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Date January 15 1982 0
Completed by J. Van Sickel Telepho.1e 319-851-5611 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE 12-1 At the beginning of the report period the plant was operating at 275 MWe, The plant was operating at reduced power levals due to lack of system demand.
12-1 During surveillance testing control building ventilation system exhaust isolation damper IV-AD-31A failed to close.
R0 Report 81-046 12-4 During surveillance testing, the trip setpoint of high drywell pressure switch PS-43118 was found to be out of tolerance.
R0 Report 81-047 12-5 A reactor scram occurred at 1949 hours0.0226 days <br />0.541 hours <br />0.00322 weeks <br />7.415945e-4 months <br /> during turbine control valve testing.
12-6 Preparations for plant startup were begun. The reactor was critical at 0205 hours0.00237 days <br />0.0569 hours <br />3.38955e-4 weeks <br />7.80025e-5 months <br />.
The generator was placed on the line at 0541 hours0.00626 days <br />0.15 hours <br />8.945106e-4 weeks <br />2.058505e-4 months <br /> and a power in;rease was begun.
12-7 The plant was operating at 281 MWe.
12-8 During nonaal operation, it was found that the output of negative 24 volt DC battery charger 1062 wa3 21 VDC.
R0 Report 81-043 12-8 During surveillance testing, both torus level indications were momentarily out of service.
R0 Report 81-049 12-14 A load increase was begun. The plant was operating at 392 MWe at 0925 hours0.0107 days <br />0.257 hours <br />0.00153 weeks <br />3.519625e-4 months <br />.
Load was decreased to 270 MWe by 2233 hours0.0258 days <br />0.62 hours <br />0.00369 weeks <br />8.496565e-4 months <br />.
12-18 A load decrease was begun in preparation for removing the unit from the line to allow repairs to the "B" reactor feedpump seal water return line.
eam unwo e CompleWd~by J. Van Sickel-Telephone 319-851-5611 NARRATIVE
SUMMARY
OF OPERATING EXPERIENCE 12-19 The generator was removed from the line at 0510 hours0.0059 days <br />0.142 hours <br />8.43254e-4 weeks <br />1.94055e-4 months <br />. The generator was again on the line at 1259 hours0.0146 days <br />0.35 hours <br />0.00208 weeks <br />4.790495e-4 months <br /> and removed from the line at 1528 hours0.0177 days <br />0.424 hours <br />0.00253 weeks <br />5.81404e-4 months <br />. The reactor was taken subcritical.
12-20 Repairs to the feedpump seal water line were completed and plant stet up was begun. The reactor was critical at 0151 hours0.00175 days <br />0.0419 hours <br />2.496693e-4 weeks <br />5.74555e-5 months <br />. The generator was j
on the line at 0556 hours0.00644 days <br />0.154 hours <br />9.193122e-4 weeks <br />2.11558e-4 months <br /> and a power increase begun.
12-23 During surveillance testing, pressure differential switch PDS-4305, which controls the reactor building to suppression chamber vacuum breaker was found with an out of specification setpoint.
R0 Report Pending 12-31 The plant was operating at 246 MWe.
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