ML20101C347

Monthly Operating Rept for Nov 1984

ML20101C347
Person / Time
Site:	Duane Arnold
Issue date:	11/30/1984
From:	Mineck D, Putnam K IES UTILITIES INC., (FORMERLY IOWA ELECTRIC LIGHT
To:	NRC OFFICE OF ADMINISTRATION (ADM), NRC OFFICE OF INSPECTION & ENFORCEMENT (IE)
References
DAEC-84-791, NUDOCS 8412210047
Download: ML20101C347 (9)

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. OPERATING DATA REPORT

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DOCKET NO. 050-0331 DATE 12-15-84 COWLETED BY Kenneth S. Putnam TELEPHONE 319-851-7456 OPERATING STATUS Notes

1. Unit Name Duane Arnold Enerav Center

2. Reporting Per!od November. 1984

3. Licensed Thermal Power (MWt):

1658

4. Nameplate Rating (Gross MWe):

565

5. Design Electrical Rating (Not MWe):

538

6. Maximum Dependable Capacity (Gross MWe):

Sa5

7. Maximum Dependable Capacity (Not MWe):

515

8. If Changes Occur in Capacity F,atings (items Number 3 Through 7) Since the Last Report, Give Reasor.s

9. Power Level to Which Restricted, if Any (Not NWels

10. Reasons For Restrictic,ns, if Any:

i This Month Y r-to-Date Cumulative

11. Hours in Reporting Period 720.0 _

8040.0 86184.0

12. Number of Hours Reactor Was critical 506.1 5693.2 61845.0

13. Reactor Reserve Shutdown Hours 0.0 150.3 150.3

14. Hours Generator On-Line 4 59.4 5661.0 60104.0

15. Unit Reserve Shutdown Hours 0.0 0.0 0.0

16. Gross Thermal Energy Generated (MWH) 408974 7750795 75449357

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17. Gross Electrical Energy Generated (MWH) 131431 2574218 25268275

18. Net Electrical Energy Generated (MWH) 121705 2418434 23657025

19. Unit Service Factor 63.8 70.4 69.7

20. Unit Availability Factor 63.8 70.4 69.7

21. Unit Capacity Factor (Using MDC Net) 32.8 58.4 53.3

22. Unit Capacity Factor (Using DER Net) 31.4 55.9 51.0

23. Unit Forced Outage Rate 36.2 15.7 17.1

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

1 Refuel Outane. February 1985

25. If Shut Down At End Of Repwt Period, Estimated Date of Startup Kf,h (9/77) 8412210047 841130 1

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s AVERAGE DAILY UNIT F0WER LEVEL DOCKET NO. 050-0331 UNIT Dueno Arnold Energy Center DATE 12-15-84 CO M LETED BY Kenne1h S. Putnam TELEPHONE 319-851-7456 MDh TH Noveer. 1984 DAY.

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

(MWe-Ne t) 1 231 17 279 2

268 18 273 3

266 19 358 4

3 20 381 5

0 21 417 6

0 22 406 7

0 23 10a 8

0 24 0

9 0

25 0

10 0

26 8

11 47 27 242 12 83 28 289 13 90 29 313 l

14 139 30 399 15 225 31 16 198 INSTRUCTIONb On this format, list the average daily unit power level in MWe-Net for each day in the reporting month. Compute to the nearest whole megawatt.

(9/77)

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rgy Ce't'r D ate 12-15-84 MAJOR SAFETY R E L AT ED WAINTENANCE Completed by Kenneth S.

Putnam Telephone 319-851-7456 C AT E SY S T EM CONPONENT DESCRIPTION 11-21-84 RHR Service Water MOV-1947 Adjusted sensitivity of position monitor to avoid unnecessary cycling.

11-23-84 A.C. P la nt P ower D i stri but ion Startup Trans f ormer D eluge Replaced a temperature ch a ng e detector and and Associate Fire Systel an associated pressure regulatcr.

Suppression System (LER 84-042) 11-30-84 Oondensate Dealneralizer Disassembled, cleaned, and inspected.

(LER 84-041) 9 O

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.e-D ocket No. 050-0331 Unit 0 uane Arnold Energy Ctr D ate 12-15-84 Completed by Kenneth Putnam Telephone 319-851-7456

_R E FU E L I NG INFORMATION 1

Name of facility.

A.

Duane Arnold Energy Center 2.'

' Scheduled date for next refueling shutdown.

A.

February, 1985 3.

Scheduled date for restart following refueling.

A.

May, 1985 4

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

Yes.

A.

Reload license submittal.

B.

Add it ional MAP LHGR curves for new fust bundles being Introduced for Cycle 8.

C.

Revised Spent Fuel Storage Technical Specifications.

D.

Supplemental Reload License submittal for Cycle 8 Lead Test Fuel Assemblies inc l ud i ng M AP LHGR curves.

5.

Scheduled date(s) for submitting proposed licensing action and supporting Information.

A.

Submitted C.

D ecember, 1984 B.

Submitted D.

Docember, 1984 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.

5 GE Lead test assemblies which incorporate advanced fuel designs will be loaded for Cycle 8.

7.

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

A.

a) 368 b) 576 i

Dockot No. 055-0331 Unit D uane Arnold Energy Ctr x

Date 12-15-84 Completed by Kenneth S. Putnam

'lelephone 319-851-7456 R E FU E L I NG INFORMATION (Continued) 8.

The-present licensed spent fuel pool storage capacity snd t t. e size of any increase in licensed storage capacity that has been requested or is planned, in

.1 umber of fuel assemblies.

A.

2050.

9.

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

A.

1998 i

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Deckot Ns. 055-0331

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U nit D ueno Arnald En ray Ctr Date 12-15-84 Completed by Kenneth S. Putnam Telephone 319-851-7456 NARRATIVE SU MM ARY OF OP ER ATi hG E XP ER I EN CE 11-01-84 At 0000 hours0 days <br />0 hours <br />0 weeks <br />0 months <br /> the plant was in run mode at 180 MWe (gross).

At 1331 hours0.0154 days <br />0.37 hours <br />0.0022 weeks <br />5.064455e-4 months <br /> a spurious electrical signal resulted in the Isolation of the Reactor Water Cloanup System.

(LER 84-039) 11-02-84 Testing of the diesel generators proved that problems with fleid ground alarms were soley Indication problems. The "B"

diesel generator was declared operable at 2152 hours0.0249 days <br />0.598 hours <br />0.00356 weeks <br />8.18836e-4 months <br /> ending the 7 day LCO.

11-04-84 At 0134. hours a catastrophic failure of the auxillary transformer was experienced. This caused a fire resulting In deluge system operation. As a result of the combination of combustion products and water, the startup transformer tripped causing a turbine trip and subsequent reactor scram.

(LER 84-040) 11-10-84 At 0625 hours0.00723 days <br />0.174 hours <br />0.00103 weeks <br />2.378125e-4 months <br /> the reactor was criticai. At 2156 hours0.025 days <br />0.599 hours <br />0.00356 weeks <br />8.20358e-4 months <br /> the reactor was driven subcritical for drywell Inspection.

At 2320 the reactor was agaln critical.

11-11-84 A reactor water conductivity excursion and the su bsequ ent testing of water chemistry Indicated that reactor water pH ha1 dropped below 5.6.

A 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> LCO commenced at 0610 hours0.00706 days <br />0.169 hours <br />0.00101 weeks <br />2.32105e-4 months <br /> for the restoration of reactor water chemistry to acceptable levels.

Reactor water conductivity and pH were brought to w ithin acceptable limits by 1850 hours0.0214 days <br />0.514 hours <br />0.00306 weeks <br />7.03925e-4 months <br />.

However, excursion of these parameters recurred and resulted in the declaration of an Unusual Event upon the initiation of plant shutdown at 2039 hours0.0236 days <br />0.566 hours <br />0.00337 weeks <br />7.758395e-4 months <br /> when conductivity exceeded 10 umho/cm. Conductivity was reduced to below 10 unho/cm by 2330 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.86565e-4 months <br /> enuing the plant shutdown requirement. Reactor water conductivity levels continueo to be a problem for several days.

(LER 84-041) 11-11-84 At 1014 hours0.0117 days <br />0.282 hours <br />0.00168 weeks <br />3.85827e-4 months <br /> the main generator was brought on line.

11-21-84 During surveillance testing a valve in the "B" RHR service water loop failed. A7 day LCO commenced at 0520 hours0.00602 days <br />0.144 hours <br />8.597884e-4 weeks <br />1.9786e-4 months <br />.

The valve and the loop were restored to normal condition by 1110 hours0.0128 days <br />0.308 hours <br />0.00184 weeks <br />4.22355e-4 months <br /> erding the 7 day LCO.

11-23-84 At 0639 hours0.0074 days <br />0.178 hours <br />0.00106 weeks <br />2.431395e-4 months <br /> the startup transformer tripped as a resu't of the spurious initiation of the fire suppression deluge system I

associated with the transformer. This resulted in a turbine trip and reactor scram from approximately 80 percent of rated power.

( LER 84-042 Pending)

x

I Docket No. 055-0331 U nit D uane Arnold Energy Ctr Date 12-15-84 Completed by Kenneth S. Putnam Telephone 319-851-7456 m

NARRATIVE

SUMMARY

OF OP ER AT I NG EX ER I ENC E (Cont) i l

11-25-84 Between 1401 hours0.0162 days <br />0.389 hours <br />0.00232 weeks <br />5.330805e-4 months <br /> on 11-25-84 and 0132 hours0.00153 days <br />0.0367 hours <br />2.18254e-4 weeks <br />5.0226e-5 months <br /> on_ 11-26-84 the reactor was cycled critical and suberltica to ma intain vessel pressure near 400 psl for inspection and testing.

l 11-26-84 At 0503 hours0.00582 days <br />0.14 hours <br />8.316799e-4 weeks <br />1.913915e-4 months <br /> the reactor was again critical. At 1735 hours0.0201 days <br />0.482 hours <br />0.00287 weeks <br />6.601675e-4 months <br /> the main generator was brought on-line.

11-30-84 At 2400 hours0.0278 days <br />0.667 hours <br />0.00397 weeks <br />9.132e-4 months <br /> the plant was in normal operation at 430 MWe gross.

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< 1, lowa Electric Light and Ibwer Company December 15, 1984 DAEC 791 Director, Office 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 November,1984 Monthly Operating Report

Dear Sirs:

Please find enclosed 12 copies of the Duane Arnold Energy Center Monthly Operating Report for November, 1984. The report has been prepared in

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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.

Very truly yours, Daniel L. Mineck Plant Superintendent - Nuclear Duane Arnold Energy Center DLM/KSP/kp*

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 Comission 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 Progran Analysis Central Iowa Power Cooperative U. S. Nuclear Regulatory Commission Box 2517 Washington, D. C. 20555 (1)

Marion, IA 52302 U. S. Nuclear Regulatory Comission Mr. George Toyne, Gen. Mgr..

ATTN: Mr. M. Thadani Corn Belt Power Cooperative Phillips Bldg.

Box 508 Washington, D. C. 20555 Humboldt, IA 50548 INPO Records Center

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1100 circle 75 Parkway i

Suite 1500 g g

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