ML20010C216

Monthly Operating Rept for Jul 1981

ML20010C216
Person / Time
Site:	Duane Arnold
Issue date:	08/14/1981
From:	Van Sickel J IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
Shared Package
ML20010C214	List: ML20010C213 ML20010C216
References
NUDOCS 8108190252
Download: ML20010C216 (7)

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OPERATING DATA REPORT DOCKET NO. 050-0331

. - . DATE Annust 14, 1981 COMPLETED IJY _J. Van Sickel TELEPl!ONE 319-851-561~c OPERATING STATUS .

1. Unit Name: Duane Arnol d Enerav Center Notes

2. Rep *orting Period: Jul v. 1981

3. Licensed Thermal Power (MWr): 1658 -

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

5. Design Electrical Rating (Net MWe): 538 .

6. Maximum Dependable Capacity (Gross MWe): 545

7. Maximum Dependable Capacity (Net MWe): 515

8. If Changes Occur in Capacity Ratings'(Items Number 3 Through 7) Since Last Report. Give Reasons:

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9. Power Level To Which Rest 4icted.lf Any (Net MWe):

10. Reasons For Restrictions. If Any:

~ This Month Yr..to Date Cumulathe

11. Ilours In Reporting Period 744 5,087 56,951

12. Number Of flours Reactor Was Critical 710.4 3,224 40,392.7

13. Reactor Reserve Shutdown Ilours 0 0 -0

14. Ilours Generator On-Line 698 3,078.9 39,355.9

15. Unit Reserve Shutdown llours 0 0 0

16. Cross Thermal Energy Generated (MWil) 895,709 4,135,155 50,133,793 .

17. Gross Electrical Energy Generated (MWil) 299,744 _,_,

1,398,443 16,801,130

18. Net Electrical Energy Generated.(MWII) 280,860 1,314,014 15,726,052

19. Unit Senice Factor 93.8% 60.5% 69.1%

20. Unit Availability Factor 93.8% _

60.5% 69.1%

21. Unit Capacity Factor (U>ine MDC Net) -

73.3% 50 2% 53.6%

22. Unit Capacity Factor (Using DER Net) 70.2% 48.0% 51.3%

23. Unit Forced Outage Rate 6.2% 6.8% 18.2%

24. Shutdowns Scheduled Over Next 6 Months (Type. Date.and Duration of Eschi: . .

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

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AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Energ; DATE August 14. 1981

- COMPLETED BY J. Van Sickel

. TELEPil0NE 319-851-5611 l

MONTil ilul y ., 19 R 1

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DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net) . (MWe-Net)

L n 317 .

17 294'

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2 325 18 402 3 0 39 467- .

4 7RR 20 ARA 5 . 345 21 494

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6 416 22 492

, 7 472 23 477 g 482 24 291

! 9 446 25 11A

) 10 497 26 327 j

• 11 437 27 , 382 12 484 28 383

~482 304 13 29 14 472 , 30 30R

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15 406 33 329 16 21 3 .

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l INS'IRUCTIONS

]- l j On this format. list the aserage daily unit power levelin MWe-Net for each day in the reporting month. Compute to i the nearest whole megawatt.

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(9/77)

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UNITSIIUTDOWNS AND POWER REDUCTIONS DOCKET NO. 050-0331 <

UNIT NAME nuano Arnold Fnergy Ctr j DATE August 14. 1981 COMPLETED BY .1 Van sickol '

REPORTMONTII Julv.1981 .

TELEPl!ONE 319-851-5611 -

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-. 3? $ Licensee j $, h,1 ,Cause & Corrective No. Date g gg g ,g g 5 Event  :; 7 E.3 Action to H

$E $ jgg Report n #G fu Prevent Recurrence 6 -

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14. 810703 F 23.8 H 3 Reactor s' crammed during turbine contro l

• valve testing apparently due to a i pressure spike causing an APRM upscale '

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15. 810715 F 22.2 H 3 Reactor s' crammed from a turbine. trip after testing and ma .:enance on the -

turbine overspeed tr .).

16. 810723 S 0 F 4 Power was reduced due to lack of system demand and to conserve fuel. .

17. 810728 S 0 F 4 Power was reduced due to lack of system demand.

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i l 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) Fife (NUREG.

D Regulatory Restriction 4 Other(Explain) 0161) u

, E Operator Training & License Examination F Administrative 5 l G-Operational Error (Explain) Exhibit 1 Same Source (9/77) 11 Other (Esplain)

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. .~~ vocket No. U50-0331

. Unit Duane Arnold Energv 0:

REFUELING INf0mtATION Date august -14.1981

. Completed by J. Van Sickel Telephone 319Th51-56ff'

1. Name of facility. <

A. Dugne Arnold Energy Center

2. Scheduled date for next refueling shutdoun.

Al Fall , 1982 ,

3. Scheduled date for restart following refueling.

A. Unknown -

. 4. Will refueling or resumption of operation thercafter require a technical specification change or other license amend, ment?

A. Yes. New. MAPLHGR tables will have to be included in Technical Specifications.

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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 supplir unrevicued design or per-formance analysis methods, significant changes in' fuel design, neu

_,, 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 nunber of fuel assemblies.

A. 2050

9. lhe projected date of the last refueling that can be discharged to the spent fuel pool assuming the present licensed capacity.

A. 1998 e

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D0cket No. 050-0331 j Unit D 13no Arnold Errrev Cortti 1

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Date Aucust 14. EB1 ^

Completed by J. Van Sic.kel MAJOR SAFETY RELATED MAINTENANCE Telephone 319-851-5611 DATE SYSTEM COMPONENT DESCRIPTION ,

7-8-81 Containment AN-8181A Installed new chemicals Atmospheric Control . t 7-10-81 Primary Containment SV-8108A Disassembled and cleaned valve 7-15-81 Containment AN-8181A Installed new chemicals Atmospheric Control -

7-21-81 Drywell Sumps IP-37B Replaced relay coil 7-21-81 HPCI HV-2200 Replace'd limit switch f

7-24-81 Neutron Monitoring LPRM 24-09A, 16-25D,16-25B,'08-17C. Replaced ' detector 7-2 *-$r Containment AN-8181A- ,

Installed new chemical's '

Atmospheric Control .

7-31-81 RCIC CV-2409 -

Replaced' limit switch, e

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Dock t No. 050-0331 Unit Duane Arnold En:rgy Center

. Date August 14, 1981 Completed By J. Van Sickel Telephone 319-851-5611 NARRATIVE SUMMAPY OF OPERATING EXPERIENCE 7- 1 At the beginning of the report period the plant was operating at 308 MWe, The power level was reduced due to lack of system demand and to conserve fuel for an extanded operating cycle.

During surveillance testing Containment Atmospheric Monitoring System (CAMS)

A was found to be operating without a sample point selected. CAMS B was inoperative at the time for surveillance testing.

R0 Report 81-029 During surveillance testing, torus atmosphere sampling line isolation valve SV-8108A would not close.

R0 Report 81 ' 30 7-3 The reactor scrammed at 0040 hours4.62963e-4 days <br />0.0111 hours <br />6.613757e-5 weeks <br />1.522e-5 months <br /> during turbine control valve testing.

The scram occurred due to an APRM upscale trip apparently caused by a pressure spike which occurred during the control valve testing.

During a control room panel check HPCI pump discharge flow indicating controller FIC-2309 was found indicating 500 GPM with the HPCI system not operating.

R0 Report 81-028 Reactor startup was begun at 1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br />. The reactor was critic 61 at 1710 hours0.0198 days <br />0.475 hours <br />0.00283 weeks <br />6.50655e-4 months <br />. The main generator was placed on the line at 1938 hours0.0224 days <br />0.538 hours <br />0.0032 weeks <br />7.37409e-4 months <br />.

Due to problems with the #3 turbine stop valve, the generator wn removed from the line at 1952 hours0.0226 days <br />0.542 hours <br />0.00323 weeks <br />7.42736e-4 months <br />.

7-4 The main generator was placed on the line at 0039 hours4.513889e-4 days <br />0.0108 hours <br />6.448413e-5 weeks <br />1.48395e-5 months <br /> and a power increase was begun.

7-8 The plant was operating at 516 MWe.

7-10 The plant was operating at 537 MWe at 0638 hours0.00738 days <br />0.177 hours <br />0.00105 weeks <br />2.42759e-4 months <br />.

7-15 During testing of the main turbine overspeed trip, the mechanical overspeed trip did not reset. A reactor scram occurred at 2017 hours0.0233 days <br />0.56 hours <br />0.00333 weeks <br />7.674685e-4 months <br /> due to a turbine trip caused by problems with the mechanical overspeed trip assembly when the trip was reset. Following the scram the main feed pumps tripped due to reactor vessel high water level and three main steam relief valves opened momentarily. The "B" feedpump was restarted at 2029 hours0.0235 days <br />0.564 hours <br />0.00335 weeks <br />7.720345e-4 months <br />. Because of the turbine trip the RPT breakers had opened. Problems were experienced in reseting the "A" breaker. Because the recirculation pumps were not restarted soon after the reactor scram, temperature stratification problems were encountered which necessitated a reactor cooldown be initiated to bring steam dome, bottom head drain and recirculation loop temperatures back within the limits for recirculation pump start.

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Docket No. 050-0331 Unit Duane Arnold Energy Center

. . Date August 14, 1981 Completed by J. Van Sickel Telephone 319-8S1-56!1

. NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 7-16 The "A" Recirc. pump was started at 0856 hours0.00991 days <br />0.238 hours <br />0.00142 weeks <br />3.25708e-4 months <br /> and the "B" recirc. pump was started at 0917 hours0.0106 days <br />0.255 hours <br />0.00152 weeks <br />3.489185e-4 months <br />. Reactor startup was begun at 0951 hours0.011 days <br />0.264 hours <br />0.00157 weeks <br />3.618555e-4 months <br />. The reactor was critical at 1324 hours0.0153 days <br />0.368 hours <br />0.00219 weeks <br />5.03782e-4 months <br />. The main generator was placed on the line at 1830 hours0.0212 days <br />0.508 hours <br />0.00303 weeks <br />6.96315e-4 months <br /> and a power increase begun.

i 7- 19 .The reactor was at rated thermal power at 1940 hours0.0225 days <br />0.539 hours <br />0.00321 weeks <br />7.3817e-4 months <br />.

7-20 The plant was operating at 531 MWe at 2236 hours0.0259 days <br />0.621 hours <br />0.0037 weeks <br />8.50798e-4 months <br />.

7-23 Plant load was reduced due to lack of system demand and to conserve fuel for an extended operatinn cycle.

7-24 The plant was operating at 305 MWe at 0640 hours0.00741 days <br />0.178 hours <br />0.00106 weeks <br />2.4352e-4 months <br />.

4 7-27 A load increase was begun. The plant was operating at 411 MWe at 0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />.

7-28 A load decrease was begun at 2355 hours0.0273 days <br />0.654 hours <br />0.00389 weeks <br />8.960775e-4 months <br />.

1 7-30 The plant was operating at 334 MWe at 0632 hours0.00731 days <br />0.176 hours <br />0.00104 weeks <br />2.40476e-4 months <br />.

I 7-31 Plant load was increased and the plant was operating at 408 MWe at 1440 hours0.0167 days <br />0.4 hours <br />0.00238 weeks <br />5.4792e-4 months <br />. A load reduction was begun at 1915 hours0.0222 days <br />0.532 hours <br />0.00317 weeks <br />7.286575e-4 months <br /> and the plant was operating at 325 MWe at 2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />.

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