ML20078K368

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Monthly Operating Rept for Sept 1983
ML20078K368
Person / Time
Site: Duane Arnold NextEra Energy icon.png
Issue date: 10/14/1983
From: Andersen M, Mineck D
IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DAEC-83-798, NUDOCS 8310190068
Download: ML20078K368 (8)


Text

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OPERATING DATA REPORT DOCKET NO. 050-0331 DATE 10-14-83 COMPLETED BY Matt Anderson TELEPHONE 319-851-7308 OPERATING STATUS Notes

1. Unit Name Duane Arnold Energy Center
2. Reporting Period September, 1983
3. Licensed Thermal Power (MWt):

1658

  1. 4. Nameplate Rating (Gross MWe): 565 (Turbine Rating)
5. Design Electrical Rating (Net MWe): 538
6. Maximum Dependable Capacity (Gross MWe): 545
7. Maximum Dependable Capacity (Not MWe):

515

8. If Changes Occur In Capacity Ratings (ltems Number 3 Through 7) Since the Last Report, Give Reasons:
9. Power Level to Which Restricted, if Any (Not MWe):
10. Reasons For Restrictions, if Any:

This Month Yr-to-Date Cumulative

11. Hours in Reporting Period 720.0 6551.0 75935.0
12. Number of Hours Reactor Was Critical 720.0 3995.3 54251.6
13. Reactor Reserve Shutdown Hours

,0 1 0.0 0.0

14. Hours Generator On-Line 1 N.0 3855.1 52790.3
15. Unit Reserve Shutdown Hours 0.0 0.0 0.0
16. Gross Thermal Energy Generated (MWH) 879727.2 4983782.4 65353302.4 l
17. Gross Electrical Energy Generated (MWH) 296 % 8.0 1672367.0 21887284.0 l
18. Net Electrical Energy Generated (MWH) 277613.5 1564415.9 20478688.3
19. Unit Service Factor 100.05 58.8%

69.5%

20. Unit Availability Factor 100.0%

58.8%

69.5%

21. Unit Capacity Factor (Using K)C Net) 74.M 46.4%

52.4%

22. Unit Capacity Factor (Using DER Net) 71.75 44.4%

50.1%

23. Unit Forced Outage Rate 0.0%

I4.5%

17.6%

24. Shutdowns Scheduled Over Next 6 Months (Type, Date, and Duration of Each):

Maintenance Shutdown 10-1-83 to 10-17-83

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 8310190068 831014 jt,t['

(9/77)

DR ADOCK 0500033

m-AVERAGE DAILY UNIT POWER LEVEL DOCKET NO. 050-0331 UNIT Duane Arnold Energy Centsr DATE October 14, 1983 COMPLETED BY Matt Andersen TELEPHONE 319-851-7308 MONTH September, 1983 DAY AVERAGE DAILY POWER LEVEL DAY AVERAGE DAILY POWER LEVEL (MWe-Net)

(MWe-Net) 1 488 17 388 2

472 18 389 3

406 19 386 4

394 20 394 5

457 21 394 6

514 22 393 7

513 23 401 8

498 24 400 9

492 25 393 10 484 26 389 11 354 27 328 12 364 28 382 13 389 29 383 14 384 30 383 13 369 31 N/A 16 392 INSTRUCTIONS On this format, list the average daily unit power level in MWe-Net for each day in the reoc* ting month. Compute to the nearest whole megawatt.

(9/77)

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Docket No. 050-0331 Unit Dueno Arnold Energy Ctr Date October 14, 1983 Completed by Matt Andersen Telephone 319-851-7308 REFUELING INFORMATION 1.

Name of facility.

A.

Duane Arnold Energy Center 2.

Scheduled date for.next refueling shutdown.

A.

Fall, 1984 3.

Scheduled date for restart following refueling.

A.

Fall 1984 4

Will refueling or resumption of operation thereafter require a technical specification change or other license amendment?

None currently identitled.

5.

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

N/A 6.

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

new or different fuel design or supplier, unreviewed design or performance analysis methods, significant changes in fuel design, new operating procedures.

None 1

The number of fuel assemblies (a) In the core and (b) In the spent fuel storage pool.

A.

a) 368 b) 576 8.

The present licensed spent fuel pool storage capacity and the size of any increase In IIcensed storage capacity that has been requested or is planned, in number of fuel assemblies.

A.

2050 9

The projected date of the last refueling thet can be discharged to the spent fuel pool assuming the present licensed capacity.

A.

1998

D ec kot Nu.

050-0331 Unit Du~

Ar mld Evrgy C~~'t r

Data Oct^b~r 14, 1983 MAJOR SAFETY RELATED MAINTENANCE _

Completed by Matt A n d e r s'e n

  • Telephone 319-851-7308 DATE SYSTEM COMPONENT DESCRIPTION 9-4-83 RCIC MO-2401 velve operator torque switch

.eplaced (R0 83-032) 9-6-83 HPCl/RCIC LIS-4531, LIS-4533 Switches recallbrated (R0 83-035) 9-7-83 RPS C71A-K12E HFA relay replaced (R0 83-034) 9-8-83 HPCI M0-2318 Valve yoke was repaired and tightened (R0 83-033) 9-10-83 Primam Containment isolation A71B-K18 HFA relay replaced (R0 83-036)

System 9-12-83 CRD Hydraulic IP-209B Complete rotating element, radial and thrust bearings and seals replaced 9-13-83 HPCI FY-2309 Square root convertor replaced 9-15-83 Neutron Monitoring "A"

SRM Amplifier replaced 9-20-83 RHR Service Water IP-22B, IP-22D Impeller on both pumps adjusted for greater pump flow 9-12-83 ti?C l IP-233 Vacuum pump motor commutator resurfaced (R0 83-038 pending)

Internal check valve repaired 9-28-83 Various Snubbers 6 Pacific Scientific Snubbers were identified for replacement during upcoming October outage 9-30-83 Neutron Monitoring "B"

RBM Repaired wiring discrepancies in RBM "B"

circuitry. (R0 83-037)

.W im i'

}

Docket No. 050-0331 Unit Duane Arnold Energy Ctr Date October 14, 1983 Completed by Matt Andersen Telephone 319-851-7308 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 9-1-83 Normal plant operation at 492 MWe.

9-2-83 At 2239 hours0.0259 days <br />0.622 hours <br />0.0037 weeks <br />8.519395e-4 months <br />, commenced reducing power approximately 3 MWe/ min.

At 2312 hours0.0268 days <br />0.642 hours <br />0.00382 weeks <br />8.79716e-4 months <br />, started control rod swap, reactor core flow <20 Md/hr.

At 2340 hours0.0271 days <br />0.65 hours <br />0.00387 weeks <br />8.9037e-4 months <br />, completed control rod swap, holding power at 50%.

9-3-83 At 0123 hours0.00142 days <br />0.0342 hours <br />2.03373e-4 weeks <br />4.68015e-5 months <br />, increasing power at approximatly 2 MWe/ min.

At 1105 hours0.0128 days <br />0.307 hours <br />0.00183 weeks <br />4.204525e-4 months <br />, HPCI minimum flow return to torus line valve MO-2318 ! n d i c a t f o r.

Intermittently showed the valve was open.

HPCI declared inop and 7-day LCO commenced.

(R0 83-033) 9-4-83 At 1532 hours0.0177 days <br />0.426 hours <br />0.00253 weeks <br />5.82926e-4 months <br />, during daily testing for HPCI Inop, RCIC outboard steam Isolation valve MO-2401 would not fully close.

RCIC declared inop and 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO commenced due to HPCI already being inop.

(R0 83-032)

At 2333 hours0.027 days <br />0.648 hours <br />0.00386 weeks <br />8.877065e-4 months <br />, RCIC system declared operable due to valve MO-2401 successfully repaired.

9-5-83 At 0103 hours0.00119 days <br />0.0286 hours <br />1.703042e-4 weeks <br />3.91915e-5 months <br />, 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO cancelled due to HPCI Inop package being completed satisfactory, HPCI 7-day LCO re-entered.

9-6-83 During surveillance testing, reactor to-lo water level switches, LIS-4531, 4533, tripped in nonconservative direction.

(R0 83-035)

During APRM scram Instrument functional tests, HFA-type relay C71A-K12E would not drop-out when de-energized by tripping APRM-E.

APRM-E was declared inop and RPS-A was manually tripped (half scram).

(R0 83-034)

D:cket No. 050-0331 Unit Duenn Arnold Energy Ctr

~ *

  • Date October 14, 1983 Complsted by Matt Andersen Telephone 319-851-7308 NARRATIVE

SUMMARY

OF OPERATING EXPERIENCE 9-8-83 At 1131 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.303455e-4 months <br />, HPCI system declared operable, end of 7-day LCO.

9-9-83 At 1840 hours0.0213 days <br />0.511 hours <br />0.00304 weeks <br />7.0012e-4 months <br />, a special visual Inspection of HFA relays discovered relay A71-K1B (reactor to-lo-lo water level) deteriorated.

1/2 group I isolation Inserted.

Relay was placed in doenergized tripped condition and LCO terminated.

(R0 83-036) 9-11-83 Plant In normal operation at 415 MWo.

Power limited to 75% due to "A"

steam line being isolated.

9-13-83 At 2131 hours0.0247 days <br />0.592 hours <br />0.00352 weeks <br />8.108455e-4 months <br />, drywell equipment drain line (containment Isolation) valve CV-3729 did not close when given a manual closure signal.

(R0 83-040) 9-15-83 At 1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br />, "B" rod block monitor declared inop, 7-day LCO commenced.

(R0 83-037) 9-18-83 Normal plant operation at 386 MWo.

9-20-83 At 1133 hours0.0131 days <br />0.315 hours <br />0.00187 weeks <br />4.311065e-4 months <br />, HPCI system declared Inop due to failure of HPCI vacuum pump motor, commenced 7-day LCO.

(R0 83-038 pending) 9-23-83 At 1649 hours0.0191 days <br />0.458 hours <br />0.00273 weeks <br />6.274445e-4 months <br />, HPCI system declared operable ending 7-day LCO.

9-26-83 Normal plant opertion at 405 MWo.

t 9-30-83 Normal plant operation at 386 MWe.

L

Iowa Electric Light and Ibwer Company October 14, 1983 DAEC 798 Director,10ffice of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, D. C.

20555 Attn: Document Control Desk

Subject:

Duane Arnold Energy Center Docket No. 50-331 Op. License DPR-49 September, 1983 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for September, 1983. The report has been prepared in accordance with the guidelines of Regulatory Guide 1.16 and distribution has been made in accordance with DAEC Technical Specifications, Appendix A, Section 6.11.1.c and Regulatory Guide 10.1.

Ver truly yo rs, M:dd Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/MWA/pf*

Enclosures File A-118d, TE-5 cc: Director, Office of Inspection Mr. Phillip Ross and Enforcement U. S. Nuclear Regulatory Connission U. S. Nuclear Regulatory Commission Maryland National Bank Bldg.

Region III Washington, D. C.

20555 799 Roosevelt Road Glen Ellyn, IL 60137 (1)

NRC Resident Inspector Director, Office of Management and Mr. Dennis Murdock Program Analysis Central Iowa Power Cooperative U. S. Nuclear Regulatory Commission Marion, IA 52302 Washington, D. C. 20555 (1)

Mr. George Toyne, Gen. Mgr.

U. 3. !bclear Regulatory Commission Corn Belt Power Cooperative ATTN: Mr. byron Siegel Box 508 Phillips Bldg. Mail 416 Humboldt, IA 50548 Washington, D. C. 20555 INPO Records Center fl 1100 Circle 75 Parkway Suite 1500 -

Atlanta, GA 30339 Duane Arnoll Energv Center e P.O. Bo.x 351

  • Cedar Rapids, Iowa 52406 e 3191851.~611